IR 05000423/1982002
| ML20042C353 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/11/1982 |
| From: | Elsasser T, Mattia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20042C350 | List: |
| References | |
| 50-423-82-02, 50-423-82-2, IEB-79-01, IEB-79-01A, IEB-79-02, IEB-79-1, IEB-79-17, IEB-79-1A, IEB-79-2, IEB-79-21, IEB-79-23, IEB-79-25, IEB-80-08, IEB-80-19, IEB-80-20, IEB-80-8, NUDOCS 8203310271 | |
| Download: ML20042C353 (17) | |
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U. S. NUCLEAR REGULATORY COMMISSION Region I Report No.
50-423/82-02 Docket No.
50-423 License No.
CPPR-113 Priority
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Category A
Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Power Station, Unit 3 Inspection at:
Waterford, Connecticut Inspection conducted: January 11-31 and February 1-23, 1982 Inspectors:
-(. M N J6
%). C. Mattia, Senior Resident Inspector date signed date signed
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date signed 8!// dk Approved by:
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T. ETs ser/' Chief, Reactor Projects da'te signed Section
, DRPI Inspection Summary:
Unit 3 Inspection on January 11-29, 1982 & February 1-23, 1982 Report No.50-423/82-02 Areas Inspected:
Routine inspection by the Resident Inspector of work activities associated with pipe erection, cable raceway erection, field procurement, calibration and maintenance of equipment and concrete placement. The inspector also perfonned plant inspection tours and reviewed licensee action on bulletins, circulars and pre-viously identified items. The inspection involved 146 inspection hours, including 8 off-shift hours by one NRC inspector.
Results:
No violations were identified.
8203310271 820312 PDR ADOCK 05000423 G
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DETAILS 1. ' Persons Contacted
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Northeast Utilities Service Company (NUSCO)
8. Carlson, Assistant Project Engineer (Berlin)
F. Comstock, FQA Technician A. Cooper, Construction Project Specialist K. Gray, Construction QA Supervisor K. Murphy, QA Construction Technician S. Orefice, Project Engineer (Berlin)
J. Putnam, Senior Construction Engineer T. Sullivan, Resident Engineer - New Site Construction S. Toth, Mew Site Construction Engineer Stone and Webster Corporation (S&W)
G. Basilesco, Engineering Assurance Engineer (Boston)
F. Bearham, QA Program Administrator (Boston)
R. B. Bradbury, Chief Licensing Engineer (Boston)
J. Carty, Head Site Extension Engineering Group W. Curtis, Lead, E. A. Engineer (Boston)
J. Flynn, Construction Supervisor, Piping R. Flodstrom, Assistant Superintendent Field QC J. G. Kappas, Superintendent of Construction J. Kelly, QA Program Administrator (Boston)
R. Ledoux, Document Control Supervisor W. MacKay, Resident Manager G. Marsh, Senior Engineer, Welding /NDE M. R. Matthews, Assistant Superintendent Field QC R. Reams, Materials Supervisor R.-Rudis, Engineering Assurance Engineer (Boston)
G. G. Turner, Superintendent, Field QC W. Vos, Field QC Engineer Westinghouse Corporation E. Harlow, Site Representative C. Peterson, Site Representative NOTE: The inspector also conferred with other licensee and contractor personnel during the course of inspection.
2.
Plant Tours The inspector observed work ~ activities in progress, completed work and
. construction' status in several areas of'the plant..The inspector examined work for any obvious defects or noncompliance with regulatory -
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requirements or license conditions.
Particular note was taken of the presence of Quality Control Inspectors and Quality Control evidence such as inspection records, material identification, nonconforming material identification, housekeeping and equipment preservation. The inspector also inspected the various preparations for concrete operations such as:
- form erection, rebar placement
- concrete placement
- concrete curing No violations were identified, 3.
Licensee Action On Previous Inspection Findings a.
(Closed) Part 21 Item (423/80-SC-02): Failure of Diesel Crankshaft Thrust Bearing. The vendor of Millstone 3's diesel generators reported that the diesels they are supplying may have similar prob-lems experienced at other nuclear plants, and the diesels will be inspected prior to shipment. The inspector reviewed the following documents related to the crankshaft failure problem:
- Northeast Utilities letter dated January 26, 1982
- Two Colt Industries' letters dated October 2,1981 The above documentation attests that the two Millstone 3 diesels were inspected to verify that the oil plugs in the oil supply system for the bearings were properly installed and that the crankshaft thrust bearing clearances were' adequate.
The inspector also reviewed a Colt Industries letter dated March 21, 1979, attesting that the 1-1/4" flared fuel lines on the two diesel generators for Millstone 3 were replaced with lines meeting the fitting manufacturer's recommendation for flares (outer diameter and radius).
b.
(Closed) ConstructionDeficiency(423/77-00-01): The licensee reported to NRC on August 10, 1977, that Westinghouse's solid state protection system (SSPS) for Millstone 3 has type AR-40 relays which experience has shown to be unreliable. The Northeast Utilities letter of June 2, 1981, to NRC, stated that the AR-40 relays will be replaced with Potter and Brumfield MDR rotary relays prior to shipping the SSPS to the Millstone 3 site. The units were received on site, and the inspector verified that the Potter and Brumfield relays were installed.
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c.
(Closed)
Item.ofnoncompliance(423/81-06-03): Mechanical Snubbers were installed without the use of the vendor's installation manual, which had specific instructions for installing and protecting the Snubbers. The inspector reviewed the licensee's corrective action, which involved removing the Snubbers that were installed and testing them in accordance witn the vendor's manual (PE-217-1) to verify that they are functional. The inspector reviewed the following S&W quality inspection reports for the testing of the Snubbers:
Inspection Report No.
Date Issued P2000056 1/21/82 P2000057 1/21/82 P2000060 1/22/82 The inspector also verified that the requisitions have been prepared and issued to fabricate Snubber mock-ups which are to be used
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temporarily, during piping erection.
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d.
(Closed)
Item of noncompliance, unresolved item and construction deficiency (81-12-01; 80-04-01 & 80-00-03):
Inadequate welding of component cooling heat exchanger supports. A Stone & Webster Non-
confonnance and Disposition report (N&D) #0991 was issued for the remaining defects (undercuts & gouge) that the contractor neglected to repair. The disposition on the report was to " accept as is" based upon a detailed stress calculation (#12179-NM (SE0)-477-HBC). The inspector reviewed the calculations to verify that the engineering evaluation of the gouge and undercut addressed the requirements of the 1974 ASMF Ill_ Code,Section NF4000. The inspector had no further questions on this item.
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(Closed) Unresolved item (423/81-06-01):
Inplace storage and
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maintenance of containment personnel hatch, The inspector reviewed
the following S&W Quality Assurance Inspection Reports for the
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correct 1.a action taken to properly maintain the personnel hatch:
Inspection Report No.
Date Correctitie Action Completed I
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S1006031 1/15/82 51006030 1/15/82 S1000272 1/15/82 S2000064 1/15/82 S2000063 1/15/82 The inspector also visually inspected the containment personnel hatch to verify corrective actions taken.
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(Closed) Unresolved item (423/81-05-10): Minimum weld size l
required at the collar to-the fillet welds on regenerative heat l
L exchanger support welds.. According to the manufacturer of the
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regenerative heat exchanger, the minimum effective thickness i
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l Westinghouse Nuclear Technology Divisions concurred with manu-
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facturer's justification, and requested a disposition
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to " accept as is".
S&W issued a N&D,No. 1118,to accept the
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fillet welds as is.
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(Closed)
Item of noncompliance (423/81-02-01 & 81-11-02)-
Failure to schedule follow-up audit for NUSCO Audit A40571.
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l The inspector reviewed the completed follow-up audit (No.A40610)'
t that was scheduled for 9/30/81 and performed on October 19-23, i
1981. The inspector also verified that the audit / survey schedule t
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l of 1/5/82 had correctly listed the follow-up audit and the close-
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out date. Objective evidence'was shown to'the inspector that l-all NUSCO QA Auditors were required to review the NUSCO QA Pro-cedure, NQA 1.14, Revision 1, and to comply with its requirements.
- The inspector also noted that an Audit No. A40569 was scheduled
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to be performed by 8/30/81, and was not accomplished until
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10/23/81. Justification for this slippage'in the schedule was.
submitted by the NUSCO Site QA Supervisor on September 24, 1981,
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to the QA Manager andl.was subsequently approved.'
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(Closed) Unresolved item (423/81-02-12): NUSCO QA Auditors were.
using various findings such as'" concerns" and " comments";that were
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I not addressed by NUSCO QA Audit Procedure NQA-1.14. Procedure NQA-i 1.14. Revision 1, now lists two (2) categories for audit results.
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" Finding" and " Unresolved Open Item". The NUSCO Site QA Supervisor i
stated that QA auditors were complying with the revised procedures.
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A random sample of audit reports, by the inspector, verified the
licensee's statement, l
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(Closed) Unresolved item (.423/81-02-15): The NUSCO QA Procedure
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NQA-1.14 was revised (Revision 1) to require scheduled audits to _
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be implemented in sixty days. The licensee has verbally comitted j
to the NRC that audits will be implemented within 30 days of.
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schedule unless prior approval, with justification, is obtained i
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i by the NUSCO Site QA Supervisor from the QA Manager,
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(Closed) Unresolved item. (423/81-02-19): The reporting of signi-l ficant construction deficiencies in accordance with 10 CFR 50.55(e)
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requirements. The inspector reviewed the following procedures which
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provide guidance for. prompt reporting.of significant and potentially i
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significant deficiencies:.
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- S&W Engineering Assurance Procedure EAP 16.2, Revision 2
- S&W Quality Standard 16.2, Revision A
- NUSCO Generation Construction Department Procedure 4.09A, Revision 1 A review of the construction deficiencies reported since the NRC construction assessment team inspection indicated that the licensee was complying with the prompt reporting of significant and potentially significant deficiencies, k.
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Item of noncompliance (423/81-12-04):
Failure of licensee's contractor to adequately control design documents (drawings, design changes and applicable nonconformance & disposition reports.) The following documents were reviewed which outlined specific correc-tive actions to improve document control on the site:
(1) NUSCO memorandum dated December 10, 1981, listing the corrective action which was taken:
- Corrected all NRC findingsof inspection 423/81-12.
- A 100% audit of all site drawing stations was conducted.
- Log developed by S&W document control for all new drawing revisions and changes with FQC verifying the implementation.
- Reducing the number of drawing stations.
- Use of correct terms for voiding / modifying documents,
- Use of correct " posting block" on documents and improve legibility of postings.
(2) S&W FQC memorandum dated 12/28/81, detailing a visit to Riverbend construction site to review their computerized system for posting changes.
In accordance with the memo, the system is very successful. During a recent 22 day period, audit results identified zero errors at the Rivertend facility, (3) S&W FQC memorandum dated 11/19/81, discussed the results of their audits from 10/30/81 - 11/13/81.
(4) S&W letter to NUSCO, dated 12/1/81, depicted the corrective action to improve document control.
(5) Minutes of a conference held on October 15, 1981, between NUSCO and their contractor to discuss various methods of improving document control.
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(6) Various S&W memos dated October 15, 1981 & October 23, 1981,
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discussing causes of problems and proposed solution.
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- The inspector also reviewed seyeral audits /in-process
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verifications /surveillances'perfomed by the licensee and his
contractor. The following'is a sununary of the results of the l
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r Date Organization Dwg. Sample Size Not Posted-
i 10/18/81 S&W FQC 1499 25.8
- 10/25/81 1055 7.4
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11/1/81 635 26.3 l
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11/8/81-1413 7.1
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11/15/81 2102 13.2-
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L-11/22/81 1752 31.2 l
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12/6/81 488 8.6
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12/13/81 483 4.6
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12/27/81 495 5.4 j
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l 1/3/82 707 3.2
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698 2.8
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2/1/82 672
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11/2/81 NUSCO QA 26~
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1/11/82 400
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i The inspector held discussions with licensee and his contractors'
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inspector-infomed them that although there is evidence that t
document control is improving, it has taken too long (approx,'3-
months) to get there.
It_ appears that the problem has been
obtaining suitable personnel in the document control organiza-
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tion. This has been corrected and S&W FQC.will continue to
i monitor their activities.
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I The inspector was informed that a new system for posting the '
design changes is scheduled to be in place by' April 1, 1982, which
- should practically eliminate all posting errors.- This item is
still considered open, and will be monitored:by'the Resident
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Inspector in subsequent inspections.
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(Closed) Unresolved item (423/81-12-02):
Fire damage to containment liner. The inspector-reviewed various documents outlining proposed repair, including instructions for cutting liner plate and taking core borings of the concrete exposed to the fire. The inspector also observed the cutting and removal of portions of the damaged liner plate, and the drilling for concrete core boring. This unresolved item is considered closed, since the licensee has reported this as a significant construction deficiency in accordance with 10CFR50.55(e), and will be inspected and reported on in future inspection reports Ts such.
(423/81-00-05).
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(0 pen) Unresolved item (423/79-11-01): The inspector reviewed the status of the NUSCO exclusion listing for specific NRC bulletins and circulars. The licensee is currently using the
" Licensing Commitment Listing" for this function. The inspector verified (sample basis) that appropriate bulletins and circulars were on the list. The licensee stated that by May, 1982, they would have a separate listing just for bulletins and circulars, similar to the Nine Mile Point 2 facility, n.
(Closed) Unresolved item (423/79-11-02): The licensee has established a system, described in S&W Procedure NEAM 31, which provides for the review and the applicability of NRC bulletins and circulars issued for "Infonnation Only". The inspector also verified that the system is functioning.
4.
Licensee Action On NRC Issued Circulars and Bulletins a.
The inspector reviewed the records relating to the following NRC circulars to verify receipt, review for applicability, and that routing of the circulars to the organizations responsible for action had been accomplished:
- Circular 77-13 (Surveillance Testing of Reactor Protection LogicCircuitry)
This circular had been reviewed by the appro3riate organizations, In addition, the licensee's operating group 1as.this circular on their coninitment follow up items list (No. 991). This circular is closed.
- Circular 78-03 (Packaging of Radioactive Material for Transport)
This circular had been reviewed by the appropriate organizations.
This item is considered open pending review,by the NRC inspector, of actions taken by the licensee's operations group.
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- Circular 78-05 (Inadvertent Safety Injection During Cooldown)
This circular had been reviewed by the appropriate organizations.
This item is considered open pending review,by the NRC inspector, of actions taken by the licensee's operations group.
- Circular 78-06 (Flooding of ECCS Room)
The inspector reviewed a S&W letter dated December 21, 1981, which stated that the Millstone 3 design was revised so that each of the RHR and containment recirculation cubical sumps will discharge to the ESF building sump.
The ESF building sump is located in an area which does not contain safety rela-ted equipment.
This circular is considered closed.
- Circular 78-13 (Inoperability of Service Water Pumps Due to High " Silt" Level)
The circular had been reviewed by appropriate organizations.
This item is considered open pending review,by the NRC inspec-tor,of actions taken by the licensee's operations group.
- Circular 78-18 (UL Fire Test Full Scale Vertical Cable Tray Array)
The inspector verified that S&W reviewed this circular for applicability and that action had been taken where appropriate.
This item is considered closed.
- Circular 79-05 (Moisture Leakage in Stranded Wire Conductors)
The inspector reviewed a S&W memo dated February 12, 1982, stating they have reviewed the circular and are addressing this item in their I EEE Equipment Qualification Program.
This item is considered closed.
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- Circular 79-10 (Pipefittings Manufactured from Unacceptable Materials)
A review by Stone & Webster and Westinghouse of their material certifications and QA data packages did not find any'pipefittings with defective material manufactured by Tube Turns Co. This item is considered closed.
- Circular 79-12 (Potential Diesel Generator Turbo-Charger Problems)
The inspector reviewed correspondence from Stone &_ Webster, and the Millstone 3 Diesel Generator Manufacturer, which indicated that this problem was not applicable to Millstone 3.
This itet is considered closed.
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- Circular 79-17 (Contact Problem with G,E, SB-12 Switches)
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The inspector reviewed S&W Problem Report PR-E-23 and the Millstone 3 response to the problem.
It was concluded th'at this circular is not appli. cable since none of these switches are used at this facility, This item is closed.
- Circular 79-18'(Proper Installation of Target Rock Safety ReliefValves)
The inspector reviewed various correspondences stating that Target Rock Safety Relief Valves are not used at the Millstone 3 plant. This item is considered closed.
- Circular 79-19 (Loose Locking Devices on Pump Impellers)
The inspector reviewed documtntation stating that a Retrofit Kit has been supplied, and 'is stored at the site with the pump internals. The locking kit will be installed when the internals are installed. This item is considered closed.
- Circular 79-20 (Failure of GTE Sylvani Relay, Type PM-CatalogSU12-11-AC)
The inspector reviewed correspondence indicating that S&W and Westinghouse do not use this relay for Millstone 3.
This item is considered closed.
- Circular 80-22 (Confirmation of Employee Qualifications)
The inspector verified that S&W and Northeast Utilities have personnel policies and procedures to verify employment refer-ences and education. This item is considered closed.
- Circular 80-23 (Potential Defects in Beloit Power Systems Emergency Generator)
The inspector reviewed correspondence from Millstone 3 Diesel Generator manufacturer stating that this circular does not apply because a Size 9 Frame Alternator is used.
This item is considered closed.
- Circular 79-24 (Proper Instrument and Calibration of Core
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Spray Pipe Break Detection Equipment)
The inspector verified that this circular was routed to various organizations for review for applicability. This review indicated that the circular did not apply to Millstone 3.
This item is considered close _ _ _ _
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- Circular 79-25 (Shock Arrestor Strut Assembly Interference)
The inspector reviewed various documents stating that only redesigned 3ergen-Petterson Part 2540 Strut Assemblies have A
been supplied to Mil stone 3; and therefore the problem should not exist.
This item :s considered closed.
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- Circular 80-07 (Problems with HPCI Turbine Oil System)
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The inspector verified that the circular was routed to the appropriate organizations to review for applicability.
The conclusion was that the problems described in the circular were not applicable to Millstone 3.
Therefore, this item is con-
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sidered closed.
- Circular 81-08 (Foundation Materials)
The inspector reviewed S&W documentation stating that this problem does not exist at Millstone 3 because most major struc>
tures are founded on bedrocks; backfill closely controlled by specifications and QA program; and that the Settlement Monitor-ing Program FCP-107 has shown no settlements greater than the expected values. This item is considered closed, b.
The inspector reviewed the records relating to the following NRC issued bul'etins to verify that receipt, review for applicability,
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and that routing of the' bulletin to organizations responsible for action has been accomplished and~that appropriate' action was taken when required:
- Bulletin 79-01 (Environmental Qualification of Class IE Equipment)
The inspector reviewed various ' licensee,,S&W and.Westinghcuse documents _to verify that an environmental qu~alification program was in-effect. The NRC Inspector informed the licensee that a detailed inspection for this item will be performed by an NRC specialist-prior to fuel loading.
This item is considered open.
- Bulletin 79-01A (Deficiencies in The Environmental! Qualification of ASCO Solenoid Valves)
.The inspector reviewed documentation-stating that all Class IE Solenoid Valves on the Millstone 3 project are qualified, and that only ASCO "NP" Series Solenoids with Class "H" coils, EPT Elastomers and no plastic parts are used in safety related systems. -This item is considered closed.
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- Bulletin 79-17 (Pipe Cracks in Stagnant Borated Water Systems atPWRPlants)
The inspector reviewed various correspondence between the licensee and Stone & Webster wh'ich-evaluated methods of eliminating the occurrence of this problem in the Millstone 3 piping systems.
An Engineering Change, E&DCR #P-P-3568, was issued to revise specifications to provide various criteria to minimize cracking of stainless steel pipe 'and welds due to ' stagnant borated water.
This item is considered closed.
- Bulletin 79-21 (Temperature Effects on Level Measurements)
The inspector verified that this bulletin was routed to the appropriate organizations. This is'under Westinghouse's scope of supply, and they have committed to submit a mechanical pro-posal by June,1982, to address the problem. This item is con-sidered open pending review of appropriate action taken by the licensee and Westinghouse.
- Bulletin 79-02, Revision 1 & 2 (Pipe Support Base Plate Designs)
The inspector reviewed various documentation concerning this item.
In accordance with the documentation, Millstone 3 complies with the S&W requirements via thsir document EMTR-612, and specification S203G.
The inspector informed the licensee that this item will be considered open.pending NRC inspection of actual implementation of this criteria at the Millstone 3 Site.
-Bulletin 79-25(FailureofWestinghouseTypeBFDRelays)
The inspector reviewed correspondence from Westinghouse and Stone & Webster stating that Type BFD Relays are not used, nor are they being planned for use, in the Millstone 3 planc.
This item is considered close. _.
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- Bulletin 79-23 (Potential Failure of Emergency Diesel Generator Field Exciter Transfomers)
The inspector reviewed correspondence between the Diesel Genera-tor manufacturer and Stone & Webster.
It was concluded that-this problem should not exist at Millstone 3 due to the wiring con-figuration. The licensee has it on their commitment list (Item 33041) to perform the 24-hour full-load operations test.
This item is considered closed.
- Bulletin 80-19 (Failures of Mercury-Wetted Matrix Relays)
The inspector reviewed correspondence from Westinghouse and Stone & Webster that Mercury-Wetted Relays are not used in Matrix Logic Applications in reactor protection systems.
This item is considered closed.
- Bulletin 80-20 (Failures of Westinghouse Type W-2 Spring Return Control Switches)
The inspector reviewed various correspondence stating that the Westinghouse Type W-2 control switches are not used in safety related circuits at Millstone 3.
This item is considered closed.
- Bulletin 80-08 (Examination of Containment Liner Penetration-Welds)
This particular item was also a significant construction o deficiency for Millstone 3, and was reported by the licensee in accordance with 10CFR50.55(e) requirements.
The inspector had previously followed this in Inspections 423/81-05 and 81-14.
This item in considered close.
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5.
Radiographic Examination of Reactor Coolant Loop Piping, Field Weld 29 & 38 A radiographic image was uncovered by an NRC inspector during inspec-tion 423/81-02. The. licensee, Westinghouse and Stone & Webster, jointly and concurrently investigated this image to determine if it was detrimental to the weld.
A Honconformance & Disposition Report No. 0860 was issued to provide various NDE techniques for evaluating this image. Both the NRC Resident and a Specialist Inspector reviewed
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the status of the investigation. (see Insp. 423/81-10). The final conclusion after a thorough investigation is that the initial indica-
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tion on the radiographic film was a demarcation between the cast stainless steel pipe and weld filler metal, and it is an acceptable indication. The inspector reviewed all the data associated with this investigation and no violations were identified.
6.
S&W Site Calibration Laboratory
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The inspector performed an inspection of the S&W Calibration Lab to verify compliance with their Quality Standard Procedure QS-12.1, Revision B, and NRC criteria. The inspector inspected the following attributes:
- Environmental conditions in lab.
- Control of damaged or obsolete equipment.
- Sources of calibration.
- Maintenance of equipment and use of procedures.
- Records (sticker program, recall system, unique identification of equipment).
- Traceability to calibration standards.
- Calibration Technician cualification and training.
- Utilization of procedures for calibrating equipment.
- Use of qualified calibration services by off-site facility.
No violations were identified.
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7.
Site Policy for Using Controlled Substances (Drugs)
The inspector verified that a policy exists on site concerning the illegal-possession or use of narcotics and/or nonprescribed drugs at Millstone 3.
A booklet is issued to all employees, describing the Millstone 3 working rules and regulations.
In the booklet it states
that " termination with no opportunity for rehire" will be the
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disciplinary action for illegal possession or use of narcotics and/
or nonprescribed drugs at Millstone 3.
In addition, warning signs are posted on the site to prohibit their use (drugs).
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8.
S&W Field Procurement
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The inspector reviewed several field requisitions and purchase orders to verify compliance with S&W ASME III Manual, Ouality Standard 4.1, and
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Engineering Assurance Pror.edure EAP 4.1.
The following field requisitions and purchase orders were reviewed:
- Requisition #297638, dated 6/4/81
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- Purchase Orders #12179-12578, dated November 3, 1981
- Requisition #331001, dated 12/17/81
- Purchase Orders #12179-14183, dated January 14, 1982
- Requisition #292788, dated 11/19/81
- 325444, 10/12/81
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- Purchase Orders #12179-12352, dated June 10, 1981
- Purchase Orders #13559, dated December 23, 1981 The inspector also reviewed the various selected vendors against the current S&W " Procurement QA Quality Rating List", Revision 095.
The inspector did not identify any violations, but expressed his concern to the licensee and the contractor that the use of excerpts of controlled
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specifications and sketches from controlled drawings did not meet the
full intent of criterion VII of Appendix B.
Specifically, Purchase Orders -#13559 and #12578, do not include' the specification or applicable drawings referenced in their associated requisitions (325444 & 297638).
the The inspector informed them that this item is unresolved pending(423/82-licensee's evaluation, and NRC ieview of S&W corporate policy.
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9.
Welding of Containment Electrical Penetrations The inspector observed the welding activities associated with the welding of three containment electrical penetrations identified as Weld Joints CI-CLP-E, Field Welds 43, 46 & 54. The welding was in accordance with S&W Weld Technique W86K, Rev. O, and Specification Requirements 2412.100-247.
The inspector reviewed the weld history data, and inspected the controlling of heat input to the electrical compogents during welding to assure that the temperature did not exceed 300 F.
The qualifica-tions of the welders were also reviewed.
No violations were identifie ___
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10.
Pipe Supports The inspector inspected two completed pipe supports, identified as SWP-2-PSA-056 and SWP-2-PSR-064,to verify the following:
- Location as specified in Dwgs. EP-190-9, BZ-19B-33 & 41.
- Weld configuration and size are in accordance with drawing requirements.
- Final welds meet specification and code requirements.
The inspector also reviewed the S&W FQC Inspection Reports P 9001023 and P 9000647 for these pipe hangers.
No violations were identified.
11. Welding of Safety Related Pipe The following weld joints in various stages of completion were inspected for compliance with ASME Code, S&W Specification 968 and various S&W Weld Technique sheets:
Weld Joint Identification Location Weld Technique CI-RCS-LP3, Field Weld #4 Containment W13B, Rev. 3 CI-RCS-LP3,
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CI-QSS-25, Field Weld #7 W22F, Rev. 3 l
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Cl-RSS-504B, Field Weld #14 W12G, Rev. 2
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CI-CHS-503, Field Weld #2 W12F, Rev. 3 l
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CI-CCP-524,
- 33 ESF Building W210, Rev. 2
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CI-SWP-295,
- 1 W29, Rev. 2
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No violations were identified.
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12. ' Reactor Coolant Piping The inspector observed portions of the rigging activities for setting the final reactor coolant pipe spool closure pieces prior to machining.
'Those observed are identified as follows:
- LP3-EC-2-
- LP2-EC-2
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- LP2-EC-1-All the above spool pieces had QC Reject Tags on them. The inspector verified that the required " Risk Releases" were issued.
The inspector, also during this inspection period, observed the machining of some closure pieces by the subcontractor (P.C.I.)
No violations were identified.
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13. Unresolved Items Unresolved items are matters about which more information is required
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in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. Unresolved item disclosed during the inspection'is discussed in Paragraph 8.
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14. Management Meetings 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.
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