IR 05000352/1980019
| ML19351G178 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/12/1980 |
| From: | Chaudhary S, Durr J, Mattia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19351G137 | List: |
| References | |
| 50-352-80-19, 50-353-80-17, NUDOCS 8102230226 | |
| Download: ML19351G178 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION O
orrtce or tuseecrton Ano euroacexcaT 50-352/ 80-19
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Report No. 50-353/ 80-17 50-362/
Docket No. 50-353/
CPFR-luo License No. CPPR-107 Priority Category A
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Licensee:
Philadelphia Electric Company 2301 Market Street Philadelphia, Pa. 19101 Facility Name:
Limerick Generating Station, Units 1 & 2 Inspection at:
Limerick, Pa.
Inspection conducted: October 7-30, 1980 Inspectors:
AMi li[/.2_f70 7.P. Durr, Senior Resident Inspector date signed Okts [. iAasi dlltlso d. Unaucnary,feactor inspector
'dats signed date signed Approved by: e-M l' fI N
'J.C. Mattia, Acting Chief Projects date signed Section, Reactor Construction and
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i Engineering Support Branch Inscection Summary:
(Unit No. 1) Inspection on October 7-30, 1980 (Report No. 50-352/80-19)
Areas Inspected:
Routine inspection by the resident inspector of structural steel, reactor vessel and internals, pipe welding and equipment storage. The' inspection also involved facility tours and review of licensee action on previously identified items.
The inspection involved 38 inspector-hours by the resident inspector.
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Results:
No items of noncompliance were identified in six of the seven areas inspected.
One item of noncompliance was identified (infraction - failure to document alterations
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l to safety-related structural steel; para. 6.)~.
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810 2280'3-@
Region I Form 12 (Rev. April 77)
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JUnitNo.2)
Inspection on October 7-30, 1980 (Report No. 50-353/80-17)
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Areas Inspected: Routine inspection by the resident inspector and a regional Essed inspector of equipment storage, reactor vessel internals, and concrete placement. The inspection involved facility tours and review of licensee action on previous inspection findings. The inspection involved 42.5 inspector-hours by the resident and regional based inspectors.
Results:
No items of noncompliance were identified in the five areas examined.
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DETAILS 1.
Persons Contacted Philadelphia Electric Company D. T. Clohecy, Quality Assurance Engiaeer (Q.A.E.)
J.M. Corcoran, Field Q.A. Branch Head M.J. McGill, Q.A.E.
G.J. Moffitt, Construction / SC Engineer Bechtel Power Corporation A. Arch, Assistant Project Field Engineer (A.P.F.E.)
B. Dragon, Q.A.E.
H.D. Foster, Project Field Q.G.E.
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H.F. Greenwalt, Q.A.E.
T. Gwin, Project Superintendent M. Jan, Area 1 Engineer
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G.C. Kelly, Q.A.E.
E.R. Klossin, Project Q.A.E.
B. Leingang, A.P.F.E.
J.L. Martin, Lead Site Q.A.E.
W. Tate, Lead Civil Engineer D.C. Thompson, A.P.F.Q.C.E.
M.G. Tokolics Q.A.E.
A.G. Weedman, Project Field Engineer R. Yancy, S/C Engineer
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Reactor Controls, Inc.
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K. Aspinwall, Q.C. Supervisor i
S.J. Kepler, Site Manager The above listed persons attended the exit interviews held either on October 23, 1980 or October 30, 1980. Other craftsmen, quality control technicians, or supervisors were contacted as th? inspection interfaced with their work.
2.
Plant Tours The inspector routinely toured tt e facility and outlyir.g areas inspecting ongoing work. He observed pipe and structural welding, electrical terminations, concrete placement, and warehouse and in-plant storage practices.
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The following specific items were noted:
The control rod drive hydraulic control units for Unit No. 1 are
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being received, uncrated and installed. The electrical control cable connectors were exposed after uncrating.
This was reported to the licensee, who had previously initiated a Finding Report, M-361, identifying the condition.
No items of noncompliance were identified.
~ amination of the wiring in Radiation Monitoring Channel B Terminal
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Lovinet,10C790, terminal point #7, disclosed cut insulation on the wire.
The insulation cut appeared to result from the wire contacting a sharp edge on an adjacent metal bracket. The licensee issued an Observed Condition Notice No. 1243 describing the condition. This item is considered unresolved pending disposition of the Observed Condition Notice and review by the NRC.
(352/80-19-02)
Visual examination of pipe restraint HBB-127-H1, containment atmosphere
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control, disclosed welding undercut in excess of ANSI B31.7 allowabla.
Review of quality control inspection records indicate that these welos have not been final inspected. The licensee issued Rework Notice, No.W-618, documenting the condition and directing repair. This item is unresolved
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pending disposition.
(352/80-19-04)
3.
Licensee Actions en Previous Inspection Findinas (Closed) Unresolved Item (352/80-03-04)
The Nuclear Energy Service's " Ultrasonic Examination Procedure for Piping Welds", had two technical discrepancies which required revision. The first error was in paragraph 6.2.3. wherein reference was made to "T-maps".
This paragraph was not applicable to the Limerick site and was removed. The
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second, omitted the listing of the calibration standard LIM 26-1.013 CS from Table and Figure No. 1.
This listing has been added to Revision 4 of the procedure.
(Closed) Deviation (352/80-04-02)
Failure cf D-Mix concrete to meet strength requirements in 28 days. The licensee submitted an amendment to the PSAR, dated September 24, 1980, which describes the low test values for 5000 psi (D-Mix) concrete and presents technical justidication for its acceptance. This action has been reviewed by the Regional Staff and determined to be acceptable.
(Closed) Unresolved Item (352/80-12-12)
Inconsistency of PECO audit post conference practices with Q.A. Procedure Q. A. I. 18-11 and Q. A. I. 18-21. The licensee revised paragraphs 6.4 of Q.A.I.18-11, Revision 5 and 6.3.1 of Q.A I.18-21, Revision 5, to reflect actual practices for post audit conference 3.
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(Closed) Noncompliance (352/80-02-01)
Drawing control. The inspector identified two outdated structural drawings being used in the field. The licensee's corrective actiocs were to remove the obsolete drawings, inspect the work covered by the drawings for compliance, audit all drawing stick files for currency, and revise the Job Rule 8031-G-5 to require the signature of the responsible superintendent to acknowledge receipt of new revisions.
A randem sample by the inspector of five drawing files and thirty drawings did not disclose any discrepancies with the authorized listing for drawings.
It was also verified by review of selected Inspection / Review Forms that an insgection of stick files had been performed.
The inspector reviewed the changes that were in effect at the time of the discovery of the outdated drawings C-ll82 and C-ll83. He selected drawing C-ll82 and established that the only change in effect during the period of noncompliance was Field Change Request (FCR) C-6059F.
Examination of the affected work disclosed that this FCR was incorporated into the work.
Lastly, he examined Job Rule 8031-G-5, Revision 32, paragraph 4.2.3 and verified that drawing receipt acknowledgement signatures are required.
(Closed) Noncompliance (352/80-07-01)
RCI reactor pressure vessel (RPV) nondestruct.ve examination (NDE) control.
The licensee's corrective actions were to flush'the cited crevice to remove the liquid penetrant and hold training discussions with NDE te,hnicians who perform liquid penetrant tests. The licensee also noted 4 discrepancy between controlling specifications which invoke different revisions of the
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" Reactor Assembly, Welding, Cleaning and Storage" Specification, 22A4202.
The inspector examined the QA Training Program, dated June 23, 1980 which documented the added instructions given NDE technicians. He also inter-viewed one of the technicians and verified that he had received instructions and was knowledgeable of the requirement.
He examined the GE Material Request, SI-HH-0169, Revision 0, dated July 7,1980 and verified that the discrepancy relating to conflicting revisions of specification 22A4202 had been clarified.
(Closed) Unresolved Item (352/80-05-02)
Inconsistency of RCI " risk release" policy with Bechtel requirements. The RCI Quality Assurance Manual, Addendum LM-1, Revision 7, paragraph 16, now requirt-that, " Customer supplied items shall not be risk released by RCI without written approval by Bechtel".
4.
Reactor Coolant Pressure Boundary Piping - Welding Welding of the belcw listed pipe joints was observed and verified to comply with selected portions of the ASME III Code, Bechtel Ruality Assurance Manual - ASME Section III, Division 1, and regulatory requirements:
WELD NO.
NUCLEAR CLASS SYSTEM BWRPD-lREC-1/4 WA3 I
Reactor Recirc.
EWRPD-lREC-1 WB47 I
Reactor Recirc.
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The inspector verified fit up, alignment, weld filler material certification, welder qualification, welding documentation, and quality control activities.
No items of noncompliance were identified.
5.
Reactor Vessel and Internals Installation Prewelding activities were observed for the reactor pressure /essel low pressure coolant injection safe end to vessel nozzle weld N17A135.
It was verified that installation activities were being performed in accordance with the work traveler #LPI-79-1-12T, Revision 3 and the Detailed Weld Procedure, No. LPI-79-1-70, Revision I.
It was noted during the preliminary weld programmer setup that an uncontrolled document war being used to program the welding machine. The document had an erroneous value for the current d wn slope. The form was issued by the welders superviser as a guide. Prior to welding, the welding engineer,
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the quality control inspector and the licensee's auditor would have verified the weld programmer settings. The licensee stated that the uncontrolled documents would either be incorporated into the formal system or not used.
The inspector had no further questions at this time concerning this matter..
InsWction of the welding on the reactor in-core housings was performed for compliance with selected requirements of GE Specifications 22A2693, Reacter and Assembly Installation, and 22A4202, Reactor Assembly, ',Miding, Cleaning, Examination and Storage. The material certifications for the welding wire in use, ER308L, heat No. C4354L308L, and the liquid peretrant, No. 79J097, were reviewed.
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Arc strikes were observed on the vessel cladding adjacent to the in-core housings, Nos. 5SX-33y end 37X-24y. The welder and quality control technician did not appear to be knowltidgeable about the proper method for dispositioning this condition. This item is considered unresolved pending disposition of the arc strikes and verification by the NRC of a satisfactory method for identifying and dispositioning this condition.
(352/80-19-03)
6.
Containment Steel Structures and Supports Jet Barrier steel erection for Unit No. I was selected for observation of work activities. The inspectcr reviewed the specification No. 8031-C-63,
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Erection of Structural Steel, and the drawings for four structural details, 29P-3, 29P-4, 39P-1 and 42P-1. Field trimming of structural detail 39P-1 was performed such that one of the bolt holes no longer satisfied the AISC I
minimum ed a requirement. Further inspection revealed that the proper documents Md not been issued to perform the alteration as required by specification C-63, Rev1sion 3, paragraph 8.4.
The failure to properly
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document alterations to safety related structural steel is contrary to 10CFR50, Appendix 5, Criterion V and an item of noncompliance.
(352/80-19-01)
The inspector examined the quality control inspection program, QCIR: Jet Barrier Steel, Rl.00, Revision 3. Log No. R4459. He selected materials received on the Material Receiving Report, MRR 77129, and verified that selected items satisfy the applicable materials specifications.
Except as noted, no items of noncompliance were identified.
7.
Placement of Safety Related Concrete The inspector reviewed the following design documents associated with the safety related concrete placements, RS-V-905, 907 and 912, in the Unit No. 2.
Reactor Building:
Drawings:
C-163, Rev. 10 C-165, Rev. 6 C-166, Rev. 6 C-637, Rev. 9 C-770, Rev. 4 Specifications:
8031-C-61 8031-C-36 ACI-318 Based on the review of the above documents and observation of a portion of the concrete placement activities, the inspector determined that the placement was carried out as required by the applicable design documents and project specifications.
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No items of noncompliance were identified.
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Mar.agement Meetings
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At periodic intervals during the course of this inspection, meetings were held with senior plant management to discuss the scope and findings of this inspection.
The resident inspector also attended entrance and exit interviews of region-based inspectors conducted with plant management during the course of this inspection.
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Unresclved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncomplianse or deviations. Unresolved items disclosed during the inspection are discussed in paragraphs 2 and 5.
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