IR 05000322/1979012
| ML19291C182 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/11/1979 |
| From: | Mcgaughy R, Narrow L, Toth A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19291C167 | List: |
| References | |
| 50-322-79-12, NUDOCS 8001230079 | |
| Download: ML19291C182 (10) | |
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U.S. NUCLE 5R REGULATORY COMMISS W1 0FFICE OF IISPECTION AND ENFORCEMENT Region I Report No. 50-322/79-12 Docket No. 50-322 License No. CPPR-95 Priority
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Category A
Licensee:
Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 Facility Name:
Shoreham Nuclear Power Station, Unit No.1 Inspection at:
Shoreham, New York Inspection condu *ed:
t 13-16,1 79 ddf M 7!L7[77 Inspectors:
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'l Toth, R_ ac r Inspector ddte signed bW 7$
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L'. Narrow, Reactor Inspector
'date~ signeo fl8 N w-'
)i/ K 1979
R. P3 11no, Reactor Inspector
' date tigned Approved by:
/ hlNih@!tM, h9 /), j A ja R. W. McGaughy#@ief, Projects Section, cate sighdd RC&ES Branch Insoection Summary:
Inspection on August 13-16, 1979 (Report No. 50-322/79-12)
Areas Inspected:
Routine, unannounced inspection by three regional based inspec-tors of work activities and quality verification records for instrumentation installation. The inspectors also performed plant tour-inspections, reviewed licensee action on previous inspection findings, and performed followup action as necessary to resolve questions which arose during the course of the inspection of the above areas. The inspection involved 66 inspector-hours onsite by 3 NRC regional office based inspectors. The inspection connenced 8:00 p.m. outside the normal dayshift working hours at the site.
Results One apparent item of noncompliance was identified in the area of instru-mentation installation, Paragraph 3.
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1791 181 Region I Form 12 80012300 7/
(Rev. April 77)
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DETAILS 1.
Persons Contacted Long Island Lighting Company T. W. Catchpole, Section Supervisor, Field QA R. De Rocher, QA Engineer D. Durand, Operations QA Engineer
- T. F. Gerecke, Engineering QA Manager
- B. R. McCaffery, Project Engineer
- W. J. Museler, UNICO Assistant Project Manager E. J. Nicholas Section Supervisor, Field QA
- J. P. Novarro, Project Manager
- A. W. Wofford, Vice President Stone and Webster Engineering E. Brabazon, Project Engineer
- J. A. Burgess, Senior Engineer, FQC - Engineering
- J. Carney, Assistant Project Engineer
- J. Hassett, Senior FQC Inspector P. Hawkins, Lead Startup Engineer R. Perra, FQC Chief Inspection Supervisor A. Popoli, Senior Structural Engineer P. Santoro, Document Coordinator W. C. Taylor, Assistant Superintendent, FQC Courter Company
- T. L. Casteel, QC Supervisor R. A. Kaer, SOA Senior Engineer
- J. Schmit, Assistant Superintendent, SQA J. S. Schrier, Startup Supervisor
- denotes persons in attendance at the exit interview.
2.
Plant Tour Shortly after arrival onsite the inspectors visited various parts of the plant to observe work activities in-progress, completed work and plant status.
Observations made during this general inspection of the plant were considered, as warranted, during later inspection of the construction quality 1791 182
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assurance program implementation in specific areas.
Additional plant tour inspections were also conducted at other periods over the duration of the inspection.
The inspectors examined work for any obvious defects or noncom-pliance with regulatory ability of quality control inspectors, and quality control evidence such as inspection records, material identification, nonconforming material status, inspection / process hold-point status, house-keeping and equipment preservation.
The inspectors interviewed craft personnel, supervision and quality inspection personnel as such personnel were available in the work areas.
During the facility tours, the inspector particularly looked for any uncontrolled weld electrode, and none was observed.
During a tour inspection the inspector observed the installation of pipe whip restraints in the main steam tunnel, located as shown in the Shoreham FSAR Figure 3C.2-10 (Restraints Nos. R5 through R12).
This work was in early stages of fitup.
No items of noncompliance were identified.
3.
Instrument Components / Systems - Work Observations The inspector observed work performance and completed work for the battery ventilation control system 1X41.
a.
The inspector observed that control panels 1X41 and PNLVC16, VCl7, and VC18 were mounted in three different configurations.
Panel VC16 was mounted on unistruts embedded in a concrete wall.
Panel VC17 was mountod on a concrete block wall and Panel VC18 was mounted on two vertical unistrut supports anchored only at ends of the unistruts.
The licensee stated the EDCR No. F-17876 was issued allowing control panels to be mounted in accordance with Specification SHl-159 instead of Specification SH1-319.
The inspector requested location drawings and mounting drawings for the safety related Category 1 control panels.
No drawings were available.
Section 1.4.6 of Specification SH1-159 states, in part, "The contractor shall do work in strict accordance with latest issues of approved drawings..." Section 3.4.5 of Specification SH1-159 states, in part,
" Free standing supports shall... be anchored to floor or foundation slab.
Where seismic loading requirements apply, support design sketches will be furnished by engineering or the design will be shown on the drawing. "
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Page 1-27, Line 1370-1373 of Specification SH1-319 states, in part,
" Floor or wall mounted panels shall be protected at all points of fastening with H.F. Livermore Corporation ' Vibra check' with bolt isolating bushings and washers or equal as approved by engineer and installation in compliance with manufacturers recommendations. "
The licensee was informed that failure to comply with requirements of Specification SH1-159 and SH1-319 is considered to be in noncompliance with 10 CFR 50, Appendix B, Criteria V.
(79-12-01).
b.
The inspector observed that the safety related, Category 1 temperature element enclosure 1X41 TE-018A, 018B, and 018C, mounted in battery rooms A, B, and C respectively, were fastened to a concrete block wall with toggle bolts per EDCR No. F-6485A and DCO-12503-E.
The licensee was requested to furnish the engineering design basis and calculations for determining that the toggle bolts meet seismic criteria of SH1-319 and the basis for determining that toggle bolts are equivalent to the embedded bolt specified for mounting enclosure.
The licensee could not provide information requested.
The licensee stated the information was at the Architect Engineer's Boston office.
This item is unresolved pending NRC review of licensee evaluation (79-12-02).
4.
Instrument Component / System Quality Records The inspector examined pertinent work and quality records for instrument components associated with engineered safety features actuation system to ascertain whether the records meet established procedures and whether records reflect work accomplishments consistent with NRC requirements and licensee commitments in the area of receipt inspection, materials certifi-cation and calibration.
Documents examined for this determination include:
Material Receiving Report Nos. 78-0198 and 77-6594D.
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Purchase Order Nos. 310010 and 310738.
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Purchase Specification No. 319.
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Certificate of Compliance for Temperature Elements 1XTE-018A, B, and
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C, dated November 17 and 22,1977.
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Certif1cate of Compliance for Temperature Controller 1XTC-018A, B, and
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C.
Panel Arrangement Wiring Diagram Nos. 510-N-5049 VC16PA, VC17PA, and
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VC18PA.
Calibration /Setpoint Test Procedure No. 2, DWD-1216 for Control Panels
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PNL-VC16, VC17, and VC18.
During the Quality Record review the inspector noted that the Seismic Certificate of Compliance for Control Panels IX41-VC16, VC17, and VCl8 did not meet the requirements of Purchase Specification SH1-319, Revision 1, dated June 9,1978.
Page 1-29, Line 1462-1470 of Specification SH1-319 states, in part, "That the Certificate of Compliance... shall be stamped by a registered professional engineer with a statement that he has reviewed the adequacy of the method for establishing that the seismic design requirements have been met."
Page 1-38, Line 1892-1893 of Specification SH1-319 states, in part, that,
" Seller must conclude that his equipment meets the seismic requirement of the specification."
Page 1-38, Line 1911-1913 of Specification SH1-319 states, in part, that
"... separate submittals of reports by vendor subcontractors, test contractors and consultants will be returned without review... all reports... shall be incorporated in a single seismic report under vendor's cover... for approval."
The Certificate of Compliance for the above did not meet the specification requirements noted above.
The licensee stated that the seismic test report was still in the review process.
This item is unresolved pending NRC review after completion of the licensee's review (79-12-03).
5.
Compliance with ASME Certification Requirements The inspector identified the effective date of ASME codes and audited the responsibilities of the certificate holders.
Authorizations in effect on site include:
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No. N-1513-1(N) to S&W for subcontracting; and Nos. N-2247-1(NA) and
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N-2248-1(NPT) to Courter and Company for installation and fabrication of piping subassemblies, components and component supports at the Shoreham site. These certificates were issued on the basis of an ASME survey in October, 1978.
Nos. N-1299-3(NPT) and N-1300-3(NA) to Reactor Controls, Inc. for
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fabrication and installation of piping subassemblies, components and component supports at the Shoreham site based on an ASME survey in April,1977.
The inspector audited the activities of the above organizations for confor-mance to the requirements of ASME III, Section NA3000.
No items of noncompliance were identified.
6.
Licensee Actiun on Previous NRC Inspection Findings (Closed) Unresolved Item (322/78-01-09):
Preservice inspection procedure NES-80A0467 provisions to assure detection of flaws at the material surface upon which the transducer is placed.
The inspector examined Revision 4 of procedure NES-80A0467, dated October 30, 1978.
The procedure has been revised to include full-V calibration for testing for transducer-side surface-flaws. The inspectors also interviewed responsible personnel regarding retesting of the RPV closure head welds, and examined Nuclear Energy Services Inc. letter No. 5535-99 which commits to reperformance of the RPV closure head ultrasonic examinations.
The LILC0 OA Level III engineer has included this item for followup in his open item list.
The inspector had no further questions regarding this matter.
(Closed) Noncompliance (322/78-15-01):
Failure to use qualified procedure for the pipe support welding.
The inspector interveiwed the cognizant LILC0 QA engineer and examined documents relative to S&W actions taken after meeting with the AWS personnel.
S&W has issued eleven new weld technique sheets (W1D, W19N, W19P, W19S, W19U, W19V, W68W, W200A, W39E, W39H, and W39F), which clarify joint preparation details.
Also, several welds have been identified which are planned to or have been cut out and reworked in accordance with the new procedures.
These matters are documented on Nonconformance/ Disposition Reports Nos.1983 and 1931, and S&W interoffice correspondence FQC/UNICO dated July 24, 1979.
The inspector had no further questions regarding this matter.
179; 186
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(Closed) Noncompliance (322/79-04-01): Thermal cutting of temporary a'. tach-ments from RHR heat exchanger nozzles. The inspector reviewed records of actions described in the licensee's August 15, 1979 letter to NRC.
He examined the following documents which provide for preheat and nondestructive examination of areas subject to thermal cutting, and which show that the RHR heat exchanger nozzle actual materials contained less than 0.3% carbon s'ach that if preheat had not been applied the thermal cutting would have been acceptable.
The inspector had no further questions regarding this matter.
Specific documents examined included:
Carter NR #607 and attached NDE records.
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Form U-l for Pertex heat exchangers #721501-1 and 2.
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GE QC Checklist #14, Revision 4, for the above exchangers.
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GE Data Sheet #21 A9227 AK, Revision 4, for the above.
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Taylor Forge Chemical Analyses (Heats #6033441 and 6041415).
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(Closed) Unresolved Item (322/79-04-02):
Cable insulation indents from insulation stripping tools. The inspector interviewed personnel and examined EDCR #F20161, dated April 23, 1979, which documents the corrective action to be taken when insulation damage occurs as a result and use of wire stripping tool.
The inspector found the corrective action to be acceptable.
(Closed) Unresolved Item (322/79-04-03):
Prompt corrective actions for DC0's involving adverse environmental conditions or other time dependent factors.
The inspectors interviewed quality control personnel and examined instructions and records which documented prompt followup provisions where necessary.
A July 10, 1979 memorandum to construction superintendents, issued by the site manager and the QC manager, defines a policy for FQC to identify those items requiring prompt corrective action and for construction staff to give such items same priority.
The inspector had no further questions on this item.
(Closed) Unresolved Item (322/79-04-04):
Conflicting requirements in S&W versus Cives drawings applicable to structural steel.
The inspectors interviewed the responsible LILC0 QA engineer and examined documents relative f7,i 167
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to resolution of the noted conflicts.
The documents showed that S&W has re-reviewed 80 of the 183 Cives drawings (for accurate reflection of details of S&W drawing FS-3B-8), and has found these generally acceptable.
The inspector had no further questions on this matter.
The S&W review is reflected in the following documents:
S&W 'nteroffice Correspondence MC/E0A dated July 25, 1979 FQU RE0 dated May 24, 1979 RE0/FQC dated July 17, 1979 EDCR No. F-19674, F-20761 N&D No. 2306 (Closed) Noncompliance (322/79-06-01):
Storage of HPCI, RHR, and core spray pumps contrary to storage procedures. The inspector toured the lowest elevation of the reactor building and examined the emergency cooling equipment in the area of proper storage conditions, relative to the licensee's June 19, 1979 letter to NRC.
Pipe openings were covered on equipment and general construction debris had been reduced in the area.
The inspector had no further questions regarding this item.
(Closed) Noncompliance (322/79-06-02):
Failure to initiate prompt corrective action.
The inspector reviewed a July 10, 1979 UNICO site manager and S&W FQC manager joint memorandum to construction superintendents, regarding current policy for timely correction of conditions adverse to quality.
(See also 322/79-04-03).
The inspector also interviewed the S&W senior quality control inspector relative to timing of corrective actions for matters identified by his staff, and relative to the directions in the aforementioned policy memorandum.
The inspector had no further questions on this item.
(Closed) Unresolved Item (322/79-06-05):
Measures to reduce arc strikes on piping.
The inspectors interviewed inspection personnel and toured the facility to observe measures taken to minimize arc strikes, and examined training attendance records for welders (April 26 - May 10,1979) regarding 1791 188
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avoiding arc strikes on piping.
Piping has been wrapped with a non-conductive material in many areas, and welders instructed regarding need to avoid arc strikes. The established Courter QA program procedures provide for final inspections for piping surface defects.
The inspector had no further questions on this matter.
(Closed) Noncompliance (322/79-07-03):
Failure te maintain 4 foot separation per S&W Specification SH1-343. The inspector examined the following EDCR's and found the corrective action to be acceptable:
EDCR #F-21570, dated June 14, 1979, requiring all tubing to be identified
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by color code and separation maintained on division basis.
EDCR #F-lS405A, dated June 20, 1979, transferring inspection responsi-
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bility from vendor SQA to S&W FQC.
EDCR #F-2145, dated June 21, 1979, incorporates color coding criteria
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in instrument installation Specification SH1-343.
EDCR #F-Oll41 A, includes color code requirements for non-safety related
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lines which share common root valve connection with safety related lines.
EDCR #F-21172 and 21173, dated June 14, 1979, provides disposition of
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NR-878 and 879.
Separation of small bore piping maintained by relocating small bore piping on oppcsite sides of large pipe.
The inspector had no further questions concerning this item.
(Closed) Inspection Query: The inspector interviewed personnel and examined the vendor card file of the purchasing organization to ascertain if equipment or material had been procured for this project from the following:
a.
Acme Steel (embeds with anchor studs).
b.
Control Components, Inc. (pressure operated relief valves).
c.
Industrial Piping Supply Company (steel tanks).
The inspector intended to review records relative to deficiencies reported to NRC under 10 CFR 50.55(e) from another project; however, no material was provided to Shoreham from these vendors.
The inspector had no further questions on this item.
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7.
Licensee Followup Activities Relative to Items Reported to NRC Under RJ CFR 50.55(e The inspector reviewed licensee actions regarding overgrinding of piping, discus ed in the licensee's June 22, 1978 letter to NRC.
Licensee records indicated that all repairs have been completed with the exception of four welds. Repaired welds are to be re-hydrotested.
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8.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items disclosed during the inspection are discussed in Paragraphs 3 and 4.
9.
Management Interview At the conclusion of the inspection on August 16, 1979, a meeting was held at the Shoreham facility site with representatives of the licensee and contractor organizations. Attendees at this meeting included personnel whose names are indicated by notation (*) in Paragraph 1.
The inspectors summarized the results of the inspection as described in this report.
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