IR 05000352/1978010
| ML19289D182 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/08/1979 |
| From: | Fasano A, Mattia J, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19289D175 | List: |
| References | |
| 50-352-78-10, 50-353-78-06, 50-353-78-6, NUDOCS 7902230170 | |
| Download: ML19289D182 (15) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF, INSPECTION AND ENFORCEMENT 50-352/78-10 Report No.
50-353/78-06 50-352 Docket No.
50-353 CPPR-106 License No. CPPR-107 Priority Category A
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Licensee:
Philadelohia Electric Comoany 2301 Market Street Philadelphia, P&. 19101 Facility Name:
Limerick Generating Station, Units 1 and 2 Inspection at: Limerick, Pa.
Inspection conducted: November 27-December 1 and December 6, 1978 b
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Inspectors:
. Mattip, Reactor inspector te c. A mt W da/.2[
ned
f xeactor inspector date signed rp ano,fw w I/2./79 n.
LL, A. Lerne, Reac or inspector dape signed 8 &, c&bW
' /> ]7 9 6. Walton, Keactor inspector dite signed
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date signed date signed Approved by:
N fd -9 _
au2J, M
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. ncuaugny, p rruJeca aection, 4fates %rted RC&ES Branch y
Insoection Summary:
Unit 1 Inspection on November 27 - December 1 and December 6,1978 (Re;, -t_
No. 50-352/78-10)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of work activities and records for safety-related pipe supports and restraints, fuel pool girder, pre-service inspection, reactor pressure vessel and primary containment penetration.
The inspectors also perfonned a plant tour inspection.
The Unit 1 inspection involved 98 inspector-hours onsite by four NRC regional based inspectors.
Results: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
7902230/76
Unit 2 Inspection on November 27 - December 1 and December 6,1978 (Report No. 50-353/78-06 Areas Inspected:
Routine, unannounced inspection by regional based inspectors of work activities and records for pre-service inspection and reactor pressure vessel. The inspectors also performed a plant tour inspection. The Unit 2 inspection involved 21 inspector-hours onsite by four NRC regional based inspectors.
Results:
No items of noncompliance were idantifie *
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DETAILS 1.
Persons Contacted Philadelphia Electric Company
- D. Clohecy, QA Engineer
- J. Corcoran, Field QA Branch Head
- D. DiPaolo, QA Engineer
- G. Lauderback, QA Engineer
- D. Marascio, QA Engineer
- R. Scott, Lead Construction Engineer Bechtel Power Corooration
- T. Altum, Lead Field Welding Engineer
- J. Blevins, QA Engineer
- F. Breismeister, Weld Engineer Supervisor
- B. Dragon, QA Engineer
- T. Fallon, Assistant Project Field QC Engineer
- H. Foster, Project Field QC Engineer
- J. Gwin, Project Superintendent
- A. Weedman, Project Field Engineer VSL Corporation J. Bond, Stressing Superintendent M. Kasko, Ironworker Foreman R. McCrossen, F. eld Inspector
- denotes those present at exit interview 2.
Plant Tour (Units 1 and 2)
The inspectors observed work activities in progress, completed work and plant status in several areas of the plants.
The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements.
During this tour one of the inspectors also examined the condition of the block wall separating Units 1
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and 2 cable spreading room and verified that seismic construction requirements, regarding various equipment supports, had been met.
No items of noncompliance were identified during tour, however, one item requires further inspection effort by the inspector and follow-up action by the licensee as noted below:
During the plant tour, an inspector performed a visual inspection of certain welds which will subsequently be volunetrically examined to cceply with ASME Section XI.
During this inspection the inspector observed a potential interference with preservice examinations caused by the placement of ASME Code stamp (NPP) nameplate near pipe girth welds GBB-119-1-3 and HSB-140-1-2.
This nameplate is about 1/16" thick x 4" x 6", and tack welded to the outside surface of the pipe approximately 1 inch from the weld edge. The inspector informed the licensee of the potential interference. The licensee has stated that if interference with preservice examinations occurred, the nameplate would be removed. This itec is unresolved pending review of licensee's action for this matter.
(352/78-10-01; 353/78-06-01)
3.
Fuel Pool Girder Beams (Post Tensionino) - Material Certification, Prestressinc Records, and Grout 1na Ocerations (Unit 11 a.
The inspector reviewed material certifications and test reports for the prestressing steel, anchor heads, wedges, and the composite bonded tendon system.
The confomance of data to referenced standards was spot-checked along with the timeliness of data receipt relative to the construction use of the : aterial.
Receipt inspection reports, deviation requests and Quality Control docu-ment reviews were examined, where applicable.
The above items were evaluated against criteria established in the following documents:
Limerick Generating Station Units 1 and 2, PSAR, Appendix 0
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Bechtel Specification 8031-C-57 ASTM A416-74, E328-72, and E18-74
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AISI Specification for Standard Alloy Steels (86L20),
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August 1977 VSL Quality Assurance Program for the VSL Post-Tensioning
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System, September 27, 1978 VSL Post-Tensioning System Procedures Manual for Fabrication
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and Installation of VSL E5-55 Post Tensioning Systems, Revision 7, November 1, 1977 VSL Material Control Procedure for VSL Nuclear Post-Tensioning
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System Components, July 17, 1978
The inspector examined the following documents relative to the above:
VSL Corporation Reports of Static Tensile Test 2.2 (Rev 1),
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November 22, 1976 and Cyclic Dynamic Tests (Rev 1), February 3, 1977 Pittsburgh Testing Laboratory Report of Testing of Uncoated
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Seven Wire Stress Relieved Strands, November 1, 1978 Shinko Wire Company, Ltd. Mill Sheet and Test Results
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No. E53-PSI-54, January 10, 1978 Mitsui and Co. (USA) Inc. Certification of low relaxation
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test data (Strand Heat Nos. 3759, 3760, and 3761),
November 2, 1978 Pacific Tube Co. Certificate of Tests - 86L20 Bar Material,
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March 20, 1978 Earle M. Jorgensen Co. Certified Test Reports for Anchor
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Heads, November 4, 1977 and February 15, 1978
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VSL Inspection Data Sheets for Manufacture of Seven-Wire Strand, October 8 and 10,1978 and November 15, 1978 VSL Inspection Data Sheet for Fabrication of VSL E5-55 Strand
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Anchor Heads, October 12, 1978 VSL Receiving Inspection Forms L1 thru L4
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VSL Standard Deviation Disposition Reports (SDDR) 16
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and 17 and Nonconformance Reports L1, Rev 0, and L4, Rev 0 No items of noncompliance were identified.
b.
The inspector exanined the storage condition of and corrosion protection for fourteen prestressing steel coils to verify con-formance to the requirements of Bechtel and VSL Specifications.
He confinned the proper marking and non-use of one coil which had been placed on " Hold" status during i_ts receiving inspection. VSL Tendon Installation Reports and Stres' sing Reports for all Unit 1 vertical tendons (Nos. V1 thru V18, both North and South) were reviewed for completeness and compliance with ACI Standard 318-71 requirements.
SDDR's were also reviewed to verify that they were properly dispositioned, documented and approved for any deviations from the requirements.
No items of noncompliance were identifie c.
The inspector witnessed grouting operations for some Unit i vertical tendons to include proportioning, mixing and pumping the grout, flow tests, temperature controls, and flushing operations, where required.
He reviewed grout material certifi-cations and tests to verify compliance with applicable specifi-cations.
Bechtel and VSL QC engineers were interviewed to determine the validity and timeliness of inspection requirements.
The above items were evaluated against criteria established in the following documents:
Limerick Generating Station Units 1 and 2 PSAR, Section 5
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Bechtel Specification 8031-C-57 and the VSL Post-Tensioning
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System Procedures Manual VSL SDDR 24, November 27, 1978
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Corps of Engineers Specification CRD-C79-58 ASTM C109-73 and C266-71
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AASH0 T26-70
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The inspector examined the flow cone (VSL RT3) and stop watch (Bechtel C-194) used in the time of efflux tests and confirmed their marking with current calibration stickers.
He noted that Revision 1 to VSL SDDR 25 provided approval for grout time-of-set test results in excess of the requirements of Specification C-57.
Any concern for delayed " bleeding" of the grout, caused by possibly excessive retardation as indicated by the time-of-set results, was eliminated by the licensee's ability to demonstrate that a post-grouting inspection requirement and regrouting procedure would mitigate any adverse " bleeding" effects at the top of the vertical tendons.
The inspector examined the following documents relative to grout material certification and testing:
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Pittsburgh Testing Laboratory Report (789344-A-C) of Grout for VSL Corp., November 2,1978 Bechtel Approval Form for the Lab Report of Grout, Water
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Report and Affadavit of Admixture (Intraplast-N), November 28, 1978
Sika Data Sheet INPL-670 for Intraplast-N (Manufacturer's
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Recommendations)
EL Conwell and Co. Report of analysis of water sample W-19,
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October 10, 1978 No items of noncompliance were identified; however, one item remains unresolved as discussed below.
The inspector noted that the above EL Conwell Report of analysis of water sample for the grout indcated no test results for chloride ion or sulphate ion concentration, the requirements for which are discussed in AASH0 T26-70.
Discussion with the licensee produced a Telecon, documenting conversation between Bechtel Power Corporation on-site and the San Francisco home office, which indicated that these two tests were last performed on January 10, 1974 and that the results were satisfactory.
Additionally, based upon current NRC interest in the chloride, nitrate and sulphate concentrations of grout used for tendon corrosion protection, the licensee stated that new tests of water quality to determine the concentration of those deleterious substances would be performed.
Pending availability of these test results and review of further licensee action, if required, this item is unresolved.
(352/78-10-02)
4.
Review of Preservice Inspection of Piping Welds a.
Quality Assurance Program (Units 1 and 2)
The inspector reviewed the licensee's program for compliance with the ASME, B&PV Code Section XI,1974 Edition and the Summer 75 Addenda as modified by Appendix III to Winter 75 Addenda and IWA 2232 of the Summer 76 Addenda.
The following documents were reviewed.
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Specification 8031-M-246A for Preservice and Inservice of Nuclear Piping Systems Specification 80A9007, Revision 4, dated May 30, 1978,
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Procurement Control
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Procedure 25-DC-001, Revision 1, dated July 24, 1975, Data Control System
Procedure 25-PQ-002, Revision 1, dated April 7,1977,
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Certifying Visual Examination Personnel Procedure 99-CNTP-001, Revision 1, dated August 18, 1978,
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Training, Testing and Certification of Nondestructive Test rersonnel Specification 80A9035, Revision 0, dated June 15, 1978,
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titled - Weld Marking Datum Points and Identification The inspector determined that: 1) these documents contain pro-visions and requirements for the administration, control and execution of the examinations which are scheduled to be conducted; 2) the implementing procedures had been approved by the licensee; 3) the ISI program and the contractor's QA manual delineates the administrative and organizational responsibilities and defines the duties of the examiners; 4) audits, including frequency, criteria, basis for re-audit, management review and assessment, corrective action and followup and documentation of results as defined; and, 5) implementing procedures are provided for activ-ities to be performed and are reviewed, approved, controlled and accessible to examiners implementing these procedures.
Procedures are also established for identification and correction of con-ditions adverse to quality.
No items of noncompliance identified.
b.
NDE Procedures The inspector audited selected implementing NDE procedures for technical adequacy and compliance with requirements of the applicable code.
The procedures audited included:
80A1561, Revision 1, dated October 18, 1978, titled - Visual
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Examination 80A9053, Revision 0, dated October 2,1978, titled - Ultrasonic
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Instrument Linearity Verification
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80A1565, Revision 2, dated October 24, 1978, titled - Ultrasonic Examination, General Requirements
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80A1566, Revision 0, dated October 25, 1978, titled - Ultrasonic Examination, Piping Welds
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80A1562, Revision 1, dated October 18, 15'78, titled -
Liquid Penet. ant
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80A1564, Revision 0, dated September 12, 1978, titled -
Radiographic Examination 80A1563, Revision 1, dated October 18, 1978, titled -
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Magnetic Particle Examination The inspector considered the above procedures with regard to criteria delineated in 10 CFR 50.55.a(g) and the ASME Boiler and Pressure Vessel Code,Section XI.
This included, but was not limited to the parameters described below for liquid penetrant, magnetic particle, radiography and ultrasonic examination techniques.
Liquid Penetrant Techniques (1) The examination method is consistent with the ASME Code requirements.
(2) Surface preparation requirements are specified.
(3) The method of penetrant application and dwell times are specified.
(4)
Component temperature is stipulated.
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(5)
Evaluation and acceptance criteria are specified and are consistent with applicable ASME Code requirements.
U1trasonic Examination Technique (1)
The type of apparatus, including frequency range, is specified.
(2)
Examination coverage, beam angle and transducer size are specified.
(3)
Calibration is accomplished on notches and scanning sensitivity is defined and is consistent with ASME Code requirements.
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(4)
Evaluation, recording and acceptance standards for flaw indications are specified and consistent with the applicable ASME Code requirement Radiographic Examination Technique (1) The type of radiation source, film type, source to film distance, exposure conditions, film density, penetrameter selection and placement are specified.
(2) Acceptance criteria is specified.
Magnetic Particle Technique (1) Prod spacing and amperages are specified.
(2) Acceptance criteria is specified and corresponds with Section XI.
The inspector noted this procedure only contained acceptance standards for examination of stud material.
However, the procedure was written for general application and could be applied to components other than stud material.
The licensee stated that this procedure would be revised prior to its use to include appropriate acceptance standards.
This item is unresolved pending a review of the revised procedure.
(352/78-10-03)
With the exception of the above unresolved item, the procedures were found to be consistent with requirements of the PSI Program and Section XI of the ASME Code referenced therein.
No items of noncompliance were identified..
5.
Safety-Related Pipe Support and Restraint Systems - Work Activities Unit 1 The inspector interviewed licensee personnel, reviewed quality control inspection reports, and visually inspected nine pipe supports and restraint system in progress of installation.
a.
Dynamic Pipe Supports The inspector visually inspected five mechanical snubbers (arrestors) to the latest drawing at the time of the inspection.
The snubbers were in systems in progress of installation.
The mechanical snubbers were examined for deterioration, corrosion, deformation, fastners, obstructions and cleanliness.
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The following mechanical snubbers, as designated by drawing number, were examined:
Succort (Revision)
Tvoe Load Pounds Stroke-Inches GBB-ll6-H38 (2)
PSA-1 1,500
GBC-104-H2 (2)
PSA-3 6,000
ESB-108-H19 (0)
PSA-3 6,000
GBC-102-H1 (4)
PSA-3 6,000
GBB-101-H13 (2)
PSA-10 15,000
The inspector on examining mechanical snubber GBB-ll8-H10 noted that the drawing, revision 3, has a change from mechanical snubber to a strut.
Documentation was examined to assure that the licensee had proper control over the change.
The inspector reviewed rework notice No. 2439, November 2,1978, which attests to the change.
The cold set was checked for the above mechanical snubbers. The cold sets were found to be within + 1/2 inch which meets the acceptance criteria for cold set. -
The following Quality Control Inspection Reports were reviewed with respect to the above listed mechanical snubbers:
M51-GBB-116-5-12 M51-GBC-104-5-3 M55-EBB-108,4/20/78 M51-GBC-102-5-1 Mechanical suppressor GBC-104-P2 as shown in revision 2 requires 5/8 inch diameter six-inch studs for base plate attachment.
Checks indicate that at least one threaded stud is greater than six inches long.
The unit remains to be grouted. The use of the longer stud rai es a prograrratic concern for thread engagement for studs used with concrete expansion type anchors.
This is an unresolved item pending the licensee's review of QCIR P-210 item 2.6 for the imple-mentation of his program to assure that minimum thread engagement is being attained for anchor attachments.
(352/78-10-04)
The inspector noted that one of the mechanical suppressor attachment bolts was loose.
The licensee is currently incorporating instructions to assure that this type of attachment is checked for required torqu.
Mechanical suppressor GB2-101-H13 was checked for grouted-in threaded rods.
The inspector reviewed QCIR No. C-64-QA-1-2, Anchor Test Report June 20, 1978 and QCIR-101-1-6-1 grouting inspection report.
No items of noncompliance were identified, b'
Pipe Component Support Structures
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The inspector visually examined four pipe support systems to the latest drawing revision at the time of the inspection.
The systems were in progress of installation.
The pipe component support structures were examined for location, acceptable welds, lubricants where applicable, material as specified by drawing and bolting requirements.
The following systems, as designated by drawing number, were examined:
Support (Revision)
Type GBB-ll6-H30(2)
Strut Assembly GBB-ll3-H3 (4)
Box Restraint HBC-182-H1 (2)
Box Restraint GBB-ll3-H27 (3)
U-Bol t The inspector reviewed records for GBB-ll3-427 with respect to grouting and anchor testing quality control.
The document reviewed was QCIR C-64-QA-1-4.
The inspector examined two nonconformance reports (NCR); No.
3402 with respect to system EBB-108-H19, and NCR No. 3401 with respect to system GBB-ll6-H39.
The NCR's required review for welding size and location corrections.
Support HBC-182-H1 was found to lack specified clearances and will require rework.
The licensee has initiated the In Process Rework Notice No. P342 which documents the rework to be performed.
This is an unresolved item pending the completion of the rework activity and re-inspection.
(352/78-10-05)
No items of noncompliance were identif'ied.
6.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved item (352/78-06-01): Dual unit snubber for Unit 1 core spray cooling system involving: safety locking wire; lock nut
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thread engagement; and torquing criteria.
The inspector reviewed Specification 8031-P-319, Revision 5.
The revision clarifies the acceptance criteria for safety wire placement, lock nut thread engage-ment and torquing criteria.
The installation details and QC verifi-cation require further definition for implementation.
This item remains unresolved.
7.
Review of Quality Records for Containment Penetrations (Unit 1)
The inspector reviewed various records associated with the mainsteam primary containment penetration for the "D" steam line.
The records were reviewed to detennine if the requirements of the specification (21A9416 Rev. 0), Purchase Order (205-AE642 Revisions 1-4) and Drawing (131C7525 Rev. 2) were adhered to for the following activities:
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Material requirements Receipt inspection
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Installation
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Testing The specific records reviewed were as follows:
Material Test Report (Heat No. 2V2569)
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Manufacturers Final Dimension Check-Sheet dated April 5, 1973 Ultrasonic Test Report dated March 27, 1973
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Magnetic Partical Test Report dated March 27, 1973
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Certificate of Compliance dated August 15, 1975
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Deviation Disposition Request No. 7374 and 7370
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Material Receiving Report No. PE-1000 and PE 922
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G.E. Product Quality Certification dated September 10,1974 and
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December 18, 1974 Nonconformance Report No. 737
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Field Discrepancy Disposition Request No. HHI-019
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Weld History Card (WR5)
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Radiography Report PBT-RT-1548
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LiqJid Penetrant Test Report PBT-PT-731
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No items of noncompliance were identified, however, the inspector noted that the job rule R-10, Revision 12, instructions for warehouse material / equipment withdrawal (Paragraph 4.3), is not specific in stating that when NSSS equipment is withdrawn from storage, for installation, it is to be reinspected (final inspection) as required by the project procedure G-5.1.
The licensee stated they would revise the job rule.
This item is considered unresolved pending review of revision to the job rule.
(352/78-10-06)
8.
Review of GA Audit Reports for Reactor Vessel Installation and Storace (Units 1 and 2)
The inspector reviewed the site QA organization's (A/E and licensee)
audit and surveillance reports related to the reactor pressure vessel installation and storage activities, to determine compliance with QA program and regulatory requirements.
The following reports were reviewed:
Bechtel Reports Work Plan and Log (Surveillance Reports) for periods March 16,
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1977 to March 31, 1977 and December 1,1977 to December 15, 1977 Audit Reports No. PFA-142 and PFA-185
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Licensee Reports Site Audit Reports Nos. M-222, M-114, M-108, M-135, C-084, C-
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089 and C-092 No items of noncompliance were identified.
9.
Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Six unresolved items disclosed during this inspection are discussed in paragraphs 2, 3, 4, 5 and.
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10. Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on December 1 and December 6, 1978.
The inspector sumarized the purpose and the scope of the inspection and the findings.