IR 05000352/1981011
| ML20010G221 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/25/1981 |
| From: | Durr J, Mccabe E, Varela A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20010G190 | List: |
| References | |
| 50-352-81-11, 50-353-81-09, 50-353-81-9, NUDOCS 8109150452 | |
| Download: ML20010G221 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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Region I 50-352/ 81-11 Report No.50-353/ 81-09 50-352~
Docket No.
50-353 CPPR-106
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License No.
CPPR-107 Priority
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Category A
Licensee:
Philadelphia Electric Comoany 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Limerick Generating Station. Unit Nos. 1 and 2 Inspection at: Limerick, Pennsylvania Inspectioncondycted:
Inspectors:
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_tets4 J 7/f,N /
J. P. Durr, Senior Resident Inspector
'date signed
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A. A. Var 81'a, Reactor Inspector date signed date signed
E Approved by: _
L. McLaDe, Unier, Ke6ctor d3te' signed
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Projects Section 2B Inspection Summary: (Unit No.1) Inspection on July 1-24, 1981.(Report No. 352/81-11)
Areas Inspected: A routine, unannounced inspection of pipe welding, lakes and dams--
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safety related structures, and licensee's actions on previous inspection findings.
The inspection involved 38.5 inspection-hours by the resident inspector and one regional based inspector.
Results: No noncompliances were identified in the four areas inspected.
(Unit No. 2) Inspection on July 1-24, 1981 (Report No. 353/81-09)
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Areas Inspected:
A routine, unannounced inspection of pipe welding, lakes and dams,
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and licensee's action on previous inspection findings. The inspection involved 25.5 inspection-hours on site by the resident inspector and a regional based specialist.
Results:
One noncompliance was identified in the three areas inspected (failure to comply with drawing requirements for a shop fabricated pipe weld.)
Region I Form 12 (Rev. April 77)
8109150452 810827 PDR ADOCK 05000352 (n PDR
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DETAILS 1.
Persons Contacted Philadelphia Electric Canpany D. T. Clohecy, Quality Assurance Engineer (QAE)
J. M. Corcoran, Field QA Branch Head F. J. Coyle, QAE
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A. G. McClean, Engineer M. J. McGill, QAE Bechtel Corporation B. A. Dragon, QAE H. D. Foster, Project Field Quality Control Engineer (PFQCE)
H. F. Greenwalt, QAE A. M. Hill, Office Engineer J. L. Martin, Lead Site QAE T. Molinaro, Project Superintendent K. L. Quinter, Assistant PFQCE D. M. Shaw, Assistant Project Field Engineer W. J. Tate, Lead Site Civil Engineer D. C. Thompson, Assistant PFQCE A. G. Weedman, Project Field Engineer S. Wybranski, Subcontracts Engineer The above listed personnel attended exit interviews held on July 17 and 23, 1981.
Other craftsmen, engineers, quality control technicians and supervisors were contacted as the inspection interfaced with their work.
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Plant Tours (Unit Nos. 1 & 2)
Periodically during the inspection, tours were made of the Unit Nos.1 and 2 primary reactor containments, the reactor buildings, the control structure, and surrounding yards and shops. The inspector examined completed work, work in-progress, quality control activities, and equip-ment storage, handling, and maintenance.
He discussed the technical aspects of the work with craftsmen, supervisors, and engineers to assure work was being performed in accordance with requirements.
During a tour of the pipe fabrication shop, the inspector examined the inside of pipe spool DBB-203-1-1 and observed a root weld condition that left a distinct notch.
It appears that the counter bore does not extend unifomly around the pipe. Also, the root weld appears to have been back welded and partially ground. The drawing, DBB-203-1, Revision 3, requires the counterbore to be h" deep minimum and the inside diameter of buttwelds to be ground flush. The failure to complete the weld internal surface in accordance with drawing DBB-203-1, Revision 3, is an item of noncompliance and contrary to 10 CFR 50, Appendix B, Criterion IX.
(353/81-09-01)
The inspector observed equipment mobilization by Morrissey Incorporated for work excavating overburden material for the spray pond. This work has been subcontracted by Bechtel, work schedule indicates that the wes-terly quadrant, spray network Area A, will have rock exposed for geologist examination in mid-September,1981.
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Licensee's Actions on Previous Inspection Findings (Closed) Deficiency (352/80-12-09) Failure to mark "ZC" drawings.
Job Rule, JR-G-30, requires field originated drawing to be marked to describe their final use (incorporated into final design drawings).
Nomally, field originated drawings do not contain safety related infomation except where "as-built" infomation is recorded, such as, cut rebar or piping "FSK" isometric drawings. The licensee was recording concrete construction joint infomation on field drawings without the proper markings and this was identified as an item of l
noncompliance.
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The NRC's concern was that concrete construction joint infomation was not being properly controlled in cases where it could impact on design considerations. The licensee marked all "ZC" drawings in accordance with Job Rule JR-G-30, and added a note to drawing C-602 to clearly
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j state how concrete construction joints are to be controlled.
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s The inspector verified that the foregoing actions had been completed.
In addition, other field originated drawings were examined to verify compliance with Job Rule, JR-G-30.
Some field c. iginated drawings were not marked per Job Rule JR-G-30, however, they do not contain any safety-related information. All drawings that were examined and contained safety-related information were properly marked. This matter is closed.
(Closed) Unresolved Item (352/80-12-11, 353/80-10-02) Licensee audit findings C-214 and C-225 on completed subcontract work have not been closed out. These outstanding quality related items found by the licensee were in documentation of calibration on stressing rams used in work performed by VSL for the post tensioning the fuel pool girders. Licensee Finding Reports on above items were reviewed by the inspector and interviews were held with responsible licensee and contractor QA personnel. The inspector observed these items were adequately responded to by Bechtel Corporation. Satisfactory documen-tation was supplieo and, the problems were closed out by the licensee on August 29, 1980. Additionally, resolution of Bechtel Corporation exceptions (f:os. 34 through 41), identified in the above unresolved item, were reviewed individually by the NRC inspector and found I
satisfactorily closed out.
(Closed) Unresolved Item (352/80-21-03, 353/80-19-02) Specification for spray pond lining, No. C-95, Revision No. 1 dated May 27, 1980, does not provide adequate quality assurance of this safety-related subcontract construction activity. The inspector observed in Revision No. 2, dated May 15, 1981 that the contractor (Bechtel) will implement all applicable aspects of its QA program for this specification and specifically for
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items which interface with the subcontractor. This complies with the licensee's commitment, in the April 10, 1980 letter to establish j
QA program responsibilities on subcontracted safety-related work.
(C1csed) Unresolved Item (352/80-21-04, 353/80-19-03) The specification for spray pond excavation, No. C-94, Revision 1, dated Oce9ber 10,1980, does not provide adequate quality assurance for treatment of open joints in exposed rock.
Revision 2 dated May 5,1981, to the above specification identifies treatment if necessary, as determined by the contractor's geologist, to be in accordance with the contr < tor's established proce-dures.
Revision 2 to the above specification also ensures appropriate QA program responsibility for safety-related subcontract construction
activity by including a new section which identifies that contractor (Bechtel) will implement all applicable aspects of its QA program for this specification.
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(Closed) Unresolved Item (352/81-06-05) Weld Metal Chemistry.
The licensee invoked the proviso of ASME IX, Table Q-ll.3, Note 3, which pemits the weld metal chemistry to fall beyond ASME Section IIC limits provided it meets base metal chemistry limits. Further, the manganese content for SFA-5.4 material is not limited. This matter is clused.
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Observation of Welding Activities (Unit Nos.1 & 2)
Reactor coolant pressure boundary (ASME III, Class I) and other safety related pipe welds (ASME III, Class II and III) were selected for document review and observation of welding activities..The document reviews verified the welder's qualifications, proper welding procedures were s ployed, required nondestructive tests specified, appropriate quality control inspection points specified and signed off, and proper preheat and postweld heat treatments were required. The observation of welding consists of, where applicable, examination of the cleanliness, fitup, and alignment of the parts; proper welding equipment; purge and cover gas flow rates; electrodes and filler materials; appearance of the weld deposit; evidence of quality control activities; and proper documentation. The following welds were examined:
Weld lio.
Class System Status BWRPD-lREC1/5 WB1 I
Recirc.
Root weld & intemediate fitup, alignment GBB-102-4/2 FW 67 II RHR Fitup, alignment, root weld &
intemediate GBB-119-11/1 FW56 II Fitup, alignment, root weld DCA-318-1 FW5A I
Root weld No itens of noncompliance were identified.
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Safety Related Structures The insnector observed portions of the installation and erection of the reactor building platfom structural steel depicted on drawing C-ll77, Revision 12.
He observed rigging and handling, fitup and alignment, verified that fasteners were of the appropriate size and type, and steel shapes were of the proper sizes and weights.
No items of noncompliance were identifie..
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Exit Interview The inspectors held exit interviews with members of the licensee's staff on July 17 and 23, 1981. They discussed the scope of the inspection and their findings.
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