IR 05000423/1979007
| ML19256E387 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/06/1979 |
| From: | Cerne A, Mcgaughy R, Toth A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256E386 | List: |
| References | |
| 50-423-79-07, 50-423-79-7, NUDOCS 7911020452 | |
| Download: ML19256E387 (4) | |
Text
9
.
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
.
Report No.
50-423/79-07 Docket No.
50-423 License No.
CPPR-113 Priority Category A
--
Licensee:
Northeast Nuclear Energy Comoany P.O. Box 270 Hartford, Connecticut,96101 Facility Name:
Millstone Nuclear Power Station, Unit No. 3 Inspection At:
Millstone Unit 3, Waterford, Connecticut Inspection Conducted:
August 9-10, 1979 Inspectors:
M
% A. D.
oth, Reactor Inspector date c%
9Mn A. C. Cerne, Reactor Inspector datt date Approved by:
N/ Nd //ftbiM f I!7'/
R~.W.McGaughy,fh
, Projects Section
/ ddte RC&ES Branch Inspection Summary:
Unit 3 Inspection on August 9-10, 1979 u m ort No. 50-423/79-07)
Areas Inspected:
Routine, unannounced inspection by two regional based inspectors.
The inspectors performed a plant tour-inspection, reviewed licens-ee action on previous inspection findings, reviewed records regarding matters reported to HP;C under 10 CFR 50.55(e), and verified compliance with ASME certi-fication system requirements.
The inspection involved 12 inspector-hours onsite by two NRC regional office based inspectors.
The inspection commenced 7:00 pm outside the normal dayshift working hours at the site.
Results:
No items of noncompliance were identified.
'
1252 292 Region I Form 167 (August 1979)
7911020
.
DETAILS 1.
Persons Contacted Northeast Utilities Service Company L
A. Chatfield, Assistant Project Engineer I. W. Deshefy, Resident Civil Lagineer
- K. W. Gray, Jr., Supervisor, Construction QA
- W. J. Kornacki, Engineer, New Site Construction
- S. Orefice, Superintendent, New Site Construction
- J. F. Putnam, Resident Mechanical Engineer
- S. R. Toth, System Superintendent, Generation Construction Stone and Webster Engineering Corporation W. B. Anderson, Assistant Superintendent, Field QC L. Barberie, QC Engineer
- R. H. Lane, Superintendent of Constraction Services
- C. A. Marrs, Superintendent tf Consttuctior.
- A. Prosi, Assistant Resident Engineer
- G. G. Turner, Superintendent, Field QC
- J. L. Whedbee, Assistant Superintendent, Field QC
- Denotes those present at the exit interv:ew.
2.
Plant Tour Shortly after arrival onsite the inspectors visiteu /arious parts tf the plant to observe second-shift 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 con-struction quality assurance program implementation in specific areas.
The inspectors examined work for any obvious defects or noncompliance with regulatory requirements.
Particular note was taken of presence and/or availability of quality control inspectors, and quality control evidence such as inspection records, material identification, nonconform-ir.g material status, inspection / process hold point status, housekaeping
.nd equipment preservation.
The inspectors interviewed craft personnel, supervision and quality inspection personnel as such personnel were available in the work areas.
On the following day, the inspectors veri-fied QC inspection of the second-shift "cadwelding" activities by review-ing the appropriate witness and final inspection reports and discussing them with the senior QC civil engineer.
No items of noncompliance were identified during this general tour-inspection.
1252 293
.
.
.
3.
License Action On Pretious NRC Findings (Closed) Unresolved (423/79-05-06):
Clarification of mandatory status of Figure NB-4233-1 of ASME Section III.
The inspector examined the E&DCR-F-M-2213 which clarifies Paragraph 16.2.1 of S&W welding specifica-tion W100B.
This item is resolved.
4.
Licensee Followup Activities Relative to Items Reported to NRC Under 10 CFR 50.55(e)
a.
Diesel Generator Engine Problems Identified Dur ig a 300-Start Test The inspector interviewed the licensee assistant project engineer regardinp the atus of the corrective actions associated with the diesel pr. ;r.s described in the licensee's November 3, 1978 letter to NRC.
In addition to the fuel pump plunger seizure, exhaust rocker arm failure and lubricating oil header failures, the inspector also inquired regarding flared fuel line leaks.
The licensee representa-tive was aware of these issues and stated that each has now been cor-rected for the Millstone 3 units.
The redesigns are to be verified by prototype verification (300 start tests) on the units for the Seabrook project.
The inspector had no further questions, b.
Tubeco Quality Assurance Program The inspector examined portions of the 1979 correspondence file between Tubeco and the licensee, and considered the quality program conclusions of the licensee's January 29, 1979 letter to NRC, and its references.
The inspector noted that some work had been reassigned to ar.other vendor due to Tubeco work loads; however, there was no indication of current quality problems related to this work.
The inspector had no further questions.
5.
ASME Certification Systen. Requirements The inspector reviewed the Millstone Unit 3 P5t.R and interviewed licensee personnel to determine the extent of work and the number of contractors involved in ASME Code activities requiring certification.
Ha verified that field fabrication of certain items requiring the
"N" :, tamp had been completed by a certificate holder of a valid Millstone 3 site certifica-tion (N-1472-5).
Authorization for the planned field construction of the containment personnei air lock assembly, requiring an "N" stamp, similarly had a site extension granted to the certificate holder (N-1212), based upon an ASME nuclear survey team site audit on July 26, 1979.
The inspector noted that for code component installation and piping activities by Stone and Webster, current "NA" (N-1511) and "NPT" (N-1512)
Certificates of Authorization exist, and arrangements have been made for 252 294
.
,
.
an ASME survey team audit, leading to a site extension authority, after approximately 15% of the subject code work is completed.
Additionally, Stone and Webster Quality Standards QS-4.1 (Revision A) and QS-7.1 (Revi-sion C) discuss procurement, receipt inspection, and code data report review requirements for ASME III items.
The inspector ascertained that the quality assurance responsibilities of current ASME code certificate 5olders for Millstone 3 site work has been reviewed on a programmatic at various times during each certificate holder's continued werk at the site and has been addressed in the appro-priate ir pection reports (e.g., 75-07, 76-02, 76-04, 76-05, 77-09, 78-05,
,
and 79-02).
Subsequent to this inspection, a telephone conversation with the licensee on September 5, 1979 confirmed NUSCO's intention to delegate the responsibility for completing the Owner's Data Repoi t (Form N-3)
to his agent, the Stone and Webster Engineering Corpocition.
No items of noncompliance were identified.
6.
Other Reportable Matters The inspector inquired regarding the designated vendors for the pressure relief valves and various tanks to ascertain that appropriate corrective actions had been taken, if warranted.
The inspector's questions arose due to 50_.55(e) reports relative to the McGuire Nuclear Station.
The licensee stated that the vendors in question (Control Components Inc. and Industrial Piping Supply Company) were not involved with Millstone Units 1, 2 or '
7.
Management Interview At the conclusion of the inspection on August 10, 1979 a meeting was held at the Millstone Unit 3 site with representatives of the licensee and contractor organization.
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.
.
'?52 295