IR 05000423/1979004
| ML19247B840 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/20/1979 |
| From: | Mcgaughy R, Toth A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19247B834 | List: |
| References | |
| 50-423-79-04, 50-423-79-4, NUDOCS 7908130621 | |
| Download: ML19247B840 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region i Report No. 50-423/79-04 Docket No.
50-423 License No.
CPPR-ll3 Priority
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Category A
Licensee:
Northeast Nuclear Energy Company P.
0.' Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Power Station, Unit No. 3 Inspection at:
Waterford, Connecticut and Berlin, Connecticut Inspection conducted: April 24-26 1979
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Inspectors:
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A. [T. Toth, Reactor Inspector date signed date signed date signed Approved by:
/) e/ [//
M 5
/M/Sd./fM R'. W. McGaugny(/C,kfff, Projects Section, v' date signed '
RC&ES Branch V
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Inspection Summary:
Inspection on Aoril 24-26, 1979 (Recort No. 50-423/79-04)
Areas Insoected:
Routine, unannounced plant tour-inspection by one regional based inspector of construction work activities in progress and licensee corporate office inspection of Quality Verification Records for followup on NRC issued Circulars and Bulletins, and audit of Stone and Webster design activi ties.
The inspection involved 10 inspector-hours onsite by one NRC regional office based inspector and 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> at the licensee's corporate offices at Berlin, Connecticut.
Results:
No items of noncompliance were identified.
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0183EO Region I Form 12 7908I30h('
(Rev. April 77)
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DETAILS 1.
Persons Contacted Northeast Utilities Service Company L. Chatfield, Assistant Project Engineer
- H. Nims, Director of Generation Construction
- S. Orefice, Superintendent of New Site Construction V. L. Patuzzi, QA Design Lead Auditor G. R. P tlan, Lead Electrical Engineer i
- S. R. Totti. System Superintendent, Generation Constr ction Northeast Nuclear Energy Company R. W. Dommers, Startup Supervisor, Unit 3 Stone and Webster Engineer L. Barberie, Quality Control Engineer
- W. McKay, Resident Manager
- C. A. Marrs, Superintendent of Construction
- F. K. Sullivan, Resident Engineer
- G. G. Turner, Superintendent of Field Quality Control J. Whedbee, Assistant Superintendent of Field Quality Control
- denotes those present at the exit interview onsite April 25, 1979.
- Mr. Diadrick was advised of corporate office inspection findings April 26,1979.
The inspector also interviewed various craft, supervision, and quality control personnel, including those mentioned in paragraph 2, below.
2.
Plant Tour _
The inspector arrived onsite unannounced on April 24, 1979 and on that day and the following day performed plant tour-inspection of all work areas at the site.
The inspector interviewed craft, supervision and quality control personnel at each work location.
The inspector interviewed such personnel to ascertain their familiarity with criteria and quality program requirements, and to ascertain implementation of quality control inspection activities.
The inspector interviewed the follcwing personnel and examined their work for conformance to applicable codes and standards:
C1.SIbt1
a.
One ironworker engaged in welding of structural steel pipe support.
b.
Two ironworkers engaged in bolting of structural steel pipe support racks in the containment building annulus.
c.
Two ironworkers, a foreman and a quality control inspector, engaged in cadwelding of containment exterior wall reinforcing steel.
d.
One ironworker engaged in field fabrication of the exterior rein-forcement assembly for the containment wall around the personnel air lock.
e.
One supervisor and one quality control inspector engaged in receipt, slump testing, and pumping of concrete for the Auxiliary Building wall line 51.3, elevation 25-40 feet, (EC-37K-3-C-3178).
f.
One foreman ana one quality control / nondestructive testing inspector engaged in welding of containment dome steel liner sections.
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g.
One area supervisor engaged in general piping and pipe hanger activities in the Turbine Building.
h.
One electrician and one quality control inspector engaged in conduit installation in tne control building.
The personnel interviewed appeared knowledgeable in the quality requirements of their respective work activities.
While observing the respective work activities, the inspector identified no departures from applicable quality codes and standards.
Additionally, the inspector had observed acceptable storage conditions of component cooling heat exchangers (e.g. #3-CCP-E-lC)
and the pressurizer (#3-RCS-TK-l) (cover gas pressurization and dunnage),
and reinforcing steel and structural steel (dunnage).
No items of noncompliance were identified.
3.
Licensee Action on NRC Issued Bulletins The inspector reviewed corporate office records relating to NRC issued Bulletins, and discussed the followup actions with the responsible individuals in the licensee organization.
He verified that the Bulletins were assigned for action to appropriate management and that responsibility for subsequent future actions was delegated.
The inspector considered accuracy of the licensee's response, timeliness, evidence of described corrective action, and provisions to assure completion of defined corrective actions.
bad 5000
For the following listed Bulletins, the licensee response was within the required time frame, the required responsibilities were assigned, and corrective actions taken where required.
The inspector had no further question on these items at this time.
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(78-01) Flammable Contact-Arm Retainers in G.E. CR120A Reldys:
The inspector reviewed the basis for the licensee's February 21, 1978 reply letter to NRC.
The licensee has ascertained that no safety related equipment currently received onsite contains relays of this possible type.
The licensee's review of procurement specifi-cations ascertained that specific types of relays are designated, and the CR120A is not included in acceptable alternatives.
His review also ascertained on April 26, 1979 that no exceptions to the specification, to permit CR120A type devices, have been authorized.
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(78-02) Terminal Block Qualification:
The inspector reviewed the basis for the licensee's February 8, 1978 letter to NRC.
Several letters between NUSCo, Stone and Webster, and Westinghouse (e.g.
GEE-78-47, NEU-2752, NEC-3164) illustrate contracting activity and technical work definition to assure that equipment is environmentally qualified in accordance with IEEE-323/74 and that unprotected terminal blocks will not be used.
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(78-04) Environmental Qualification of Certain stem Mounted Limit Switches Inside Reactor Containment: The inspector reviewed the basis for the licensee's April 27, 1978 letter to NRC.
Correspondence identified as NEC 2813 and NEU 2732 indicate coordination with principal contractors to assure that the questionable limit switches are not used.
General qualification program (see 78-02 above) require-ments are expected to assure qualifications of limit switches.
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(78-05) Malfunctioning of Circuit Breaker Auxiliary Contact Mechanism -
G.E. Model CRl05X:
The inspector reviewed the basis for the licensee's June 8, 1978 letter to NRC.
A licensee letter (NEC-2863) and a responding teletype from Stone and Webster (dated June 7,1978) confirms the engi-neering plan to review all safety related equipment specifications to assure that suspect breakers will not be incorporated into the equipment.
T4 review was to be complete by August 1978 but the licensee respon-
i.1bie engineer had no record that it had been completed; he stated that this woula be verified and documented in his file.
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(78-06) Defective Cutler-Hammer Type M Relays with DC Coils. The inspector reviewed the basis for the licensee's July 27, 1970 letter to NRC.
A teletype from Stone and Webster (dated July 25,1973) confirms engireering plans to review all safety related equipment specifications to assure that the suspect relays will not be incorporated into the D.DUi 2
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' equipment.
The review was to be complete by September 1978 but the licensee responsible engineer had no record that it had been completed; he stated that this would be verified and documented in his file.
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(78-10) Bergen-Patcrson Hydraulic Shock Suppressor Accumulator Spring Coils: The inspector reviewed the basis for the licensee's July 6, 1978 letter to NRC. A document (#WGC-78-G-107) identifies Monroe suppressors in limited areas as the only hydraulic shock suppressors planned for use at the site.
4.
Licensee Action on NRC Issued Circulars The inspector reviewed licensee corporate office records and interviewed responsible personnel to ascertain that circulars had been received by responsible management, a review for applicability was performed, and appropriate corrective action taken or scheduled to be taken where necessary.
The inspector ascertained that the above activities involved participation by technical and management personnel cognizant of the substance of the circulars.
The inspector noted a project engineer instruction (NPE-79-283 dated April 4,1979) which requests review and recommendation on course of action for 1978 issued circulars, and documentation thereof.
The project engineer stated that he also plans a record review of actions taken on 1977 circulars.
The inspector concluded that review responsibility has been assigned for all 1978 and 1979 (to date) circulars.
Completion of review and definition of correctiva action has been achieved for the following:
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(78-02) Proper Lubricating Oil for Terry Turbines: This has been referred to the startup organization for action and has been entered as an action item on the Commitment Followup Program.
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(78-04) Installation Errors That Could Prevent Closing of Fire Doors:
A licensee inquiry to Stone and Webster has ascertained that the type fire door in question is not used for the Millstone 3 project.
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(78-08) Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants: The inspector examined letters and meeting notes (NEC-2944, NES-19851, NES-19425, NES-12179, GEE-79-33, NEC-3164, GEE-78-308) dating from July 1978 to February 1979 relating to qualifying equi; ment to IEEE 323/74 and documentation of such qualification. Memorandum GEE-78-308 requests the electrical lead engineer to specifically investigate the subject of the Circular 78-08.
Additional plans include having Stone and Webster list all category IE equipment, identify current environmental requ1rements for each item, review purchase orders for specification requirements consistent with current requirements, and document analysis / resolution of any deviations in vendor data.
618304
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(78-09) Arcing of G.E. NEMA Size 2 Centactors: The licensee determined that ITE motor control centers are specified and do not contain GE Starters. For other panel. vendors,.the' licensee' lead electrical engineer stated that his staff will review bills of materials to identify where additional action is required.
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(78-15) Tilting Disk Check Valves Fail to Close With Gravity in Vertical Position: The licensee has entered this item for future veri-fication action, on the Startup Group Commitment Followup List.
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(79-02) Failure of 120 Volt Vital AC Power Supplies: A January 31, 1979 interoffice memorandum and statements by the licensee lead electrical engineer show that the licensee is actively engaged in negotiations with the vendor (SCI) and other sources to resolve this problem and to obtain conformance to IEEE-323/74.
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(79-04) Loose Locking Nut on Limit Torque Valve Operators: A licensee project engineer instruc. tion (NPE-79-282) to the startup group, a Stone and Webster advisory operations field telephone record (April 19,1979),
and statements by the licensee Startup Supervisor show that the licensee startup group has assumed responsibility to stake or crimp locknuts during Phase I testing.
The Startup Supervisor stated that he had added this to his Commitment Followupit,tst.
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(79-05) Moisture Leakage in Stranded Wire Conductors: The licensee letter to Stone and Webster (NEC-3225) requests specific consideration of this item.
No interim action onsite is required in view of project status.
The inspector had no further questions on the above ite:as at this time.
No items of noncompliance were identified durina this review.
5.
Desian Audits The inspector examined records and interviewed personnel regarding licensee audits of the Stone and Webster design activity.
The inspector interviewed the group leader and a lead auditor, examined an audit schedule / record for 1974 to 1979, and examined one audit report and associated checklist, super-visor review sheet, audit schedule followup, and correspondence relating to resolution of the audit findings.
The inspector considered the above items relative to Criteria I, II, XV, XVI, XVII and XVIII of Appendix B of 10 C F R 50, and ANSI N45.2.12.
The inspector considered the scope of scheduled audits to include applicable criteria of Appendix B, timeliness and extent of followup on audit findings, measures to prevent recurrence of deficiencies, and provisions for reaudit of deficient / corrected areas.
The 23pector examined audit #A00385 and related correspondence including QM3-E-394, QM3-E-399 and NES-19632.
No items of noncompliance were identified during this review.
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6.
Management interview At the conclusion of the inspection on April 26, 1979 a meeting was held at the site with representatives of the licensee and contractor organizations.
Attendees at this meeting included personnei whose names afe indicated by notation (*) in paragraph 1.
The inspector summarized the results of the inspection as described in this report. An exit interview also was held with the Quality Assurance Manager at the conclusion of the inspection at the licensee's Berlin offices.
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