IR 05000245/1979012
| ML19207A474 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/15/1979 |
| From: | Sanders W, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19207A473 | List: |
| References | |
| 50-245-79-12, 50-336-79-15, NUDOCS 7908200066 | |
| Download: ML19207A474 (5) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report Nos. 50-245/79-12 and 50-336/79-15 Docket Nos. 50-245 and 50-336 License Nos. DPR-21 and DPR-65 Priority Category C
-
Licensee: Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Station, Unit; I and 2 Inspcetion at:
Waterford, Connecticut 06385 Inspection conducted:
May 7, 1979 through May 11, 1979 Inspector: /// / MwM 4 - g - 7f W. F., Sanders, Reactor Inspector date signed
/
/
Approved by: l[2U / $, d,4/)
h[/,'/79 I<. E. Tripp, Chief,' Engineering date signed Support Section No. 1, RC&ES Branch s
Inspection Summary:
Inspection on May 7-11, 1979 (Combined Inspection Report 50-245/79-12; 50-336/79-15 Areas Inspected:
Routine, unannounced inspection by one regional based inspector of activities related to inservice inspection and bulletins-79-02 and 79-03.
The inspection involved 32 inspector-hours on-site by one NRC regional based inspector.
Results: No items of noncompliance or deviations were identified.
7 908200 OG6 809 046
- g
.
DETAILS 1.
Persons Contacted The following technical and supervisory level persannel were contacted:
Northeast Nuclear Energy Company
- J. Opeka, Station Superintendent
- E.
Farrell, Superintendent, Unit 2
- R. Herbert, Superintendent, Unit 1 N. Goodnough, NESCO QA J. Kennan, Outage Coordinator J. Leason, ISI Coordinator, Unit 1 R. Michaud, Supervisor, Construction QC-NUSCO J. Stankoski, ISI Level III J. Stansbury, ISI Technician, Unit 2
- T. Shedlosky, NRC Resident Inspector General Electric Company M. Hart, NDE, Level III Hartford Steam Boiler Inspection and Insurance Company B. Smith, Authorized Inspector The inspector interviewed other licensee and contractor personnel.
- Denotes those present at exit interview.
2.
General This inspection was made to inspect the activities and work in progress related to the outage for inservice inspection of Unit 1 and Unit 2.
Additional inspections were of the work in progress and the licensee's actions for response to bulletins 79-02 and 79-03.
Unit 1 3.
Pipe Support Base Plate Design,Bulletin 79-02 The inspector reviewed the inspection procedure 79-1-23 and the inspection plan acceptance criteria SF201, Revision 0, for the pipe support base plates.
Prior to the completion of this inspection, 809 047
.
,
-2-the '.'.eensee's inspection program was discoatinued in favor of complete replacement of the existing platec with new plates of a heavier design and installation of new bolts.
The new plates will be located adjacent to the old plates.
The plan is to complete the essential sys*. ems before startup and do the remainder of plant later.
Within the scope of this inspection, no items of noncompliance were identified.
4.
Inservice Inspection An inspection was made of the ISI Program which was developed to comply with ASME Section XI 1974 with Summer 75 Addenda and the exclusion criteria which had been submitted and approved by NRR.
The procedures and testing results were reviewed to this criteria.
No item of noncompliance were identified.
5.
Feedwater Inner Radius Inspection The inspector reviewed the following proccdures and ultrasonic data:
-
Procedure E504P14, Revision 0, Zone 3, ID Nozzle Straight Procedure TP-508-173, Revision 0, Zone 1, Inner Radius
-
-
Procedure TP-508-174, Revision 0, Zone 2, RV Inside Straight Data Reviewed Zone 1 Zone 2 Zone 3 Asmuith Pesults N4A X
X X
No reportable ind N4B X
X X
135 No reportable ind N4C X
X X
225 No reportable ind N4D X
X X
375 No reportable ind No items of noncompliance identified.
6.
Core 0 pray "B" Loop From Notzle to Containment Penetration Raview of Procedures 160A7501, Fevision 2, and Review of Test Data for the following welds:
-
CSBJ 1
-
CSBJ 7
-
CSBJ 2
-
CSBJ 8
-
CSBJ 3
-
CSBJ 9
-
CSBJ 4
-
CSBJ 10
-
CSBJ 5
-
CSBJ 10A
-
CSBJ 6
-
CSBJ 11
-
CSBJ 11L These welds join 10" Schedule 80, A358 type 304 SS pipe.
No items of noncompliance were identified.
809 048
,
-3-7.
Clean Up Water System A Outside Containment The same procedura was used on this pipe as was used'on' the core spray.
The inspector reviewed the calibration data sheet.
The test data for the following welds which join 8" Schedule 80 A358-304 SS pipe, were reviewed:
-
CUAJ 14
-
CUAJ 20
-
CUAJ 15
-
CUAJ PB1 CUAJ 16
-
CUAJ 22
-
-
CUAJ 17
-
CUAJ 22L
-
CUAJ 18
-
CUAJ 23
-
CUAJ 19L
-
CUAJ 24
-
CUAJ 25 No items of noncompliance were identified.
Unit 2 8.
Bulletin 79-02 Pipe Support Base Plates The inspector reviewed the following documentation related to the inspection of the pipe support base plates and the actions taken by the licensee.
QCI-79-02-1, NUSCO Construction QC Instruction Inspection of a.
Category I Pipe Support Base Plates and Anchor Bolts b.
UT Procedure QCI-79-02-2 GCE-79-215, Instructions on Inspection Criteria c.
d.
Training program and instructions e.
Certifications for 8 inspectors f.
Inspection Summary of deficiencies found in the following categories:
-
Rotation of anchor bolts in hole
-
Loose nuts
-
Incorrect imbed depth
-
Lack of minimum thread engagement
-
Incorrect bolt size
-
Review of noncompliance report NCRS The review of the inspection program did not reveal any deficiencies in the program.
809 QM
'
.
-4-9.
Bulletin 79-03 Defects in the Longitudinal Pipe Welds The inspector reviewed the following documentation related to the inspection of longitudinal welds in ASME SA 312 type 304 stainless steel pipe supplied by Youngstown Welding and Engineering Company.
a.
Bechtel Drawing 25203-26015, Safety Injection System.
b.
Ultrasonic Procedure NU-UT-1, Revision 0 c.
Ultrasonic Procedure KU-UT-2, Revision 0 d.
Test data for 15 pc 12" Sch. 20 pipe,159 lineal feet which represents all of the 12' pipe in containment connecting the four safety injection tanks to the check valves.
The data shows that all of the welds were acceptable using a 60 shear wave test and calibrating to a square notch equal to 10 percent of the wall thickness.
Information was not available during this inspection to determine if any of the fitting were made by Flowline Co from Youngstown pipe.
This item should be included in the final response to the bulletin.
No items of noncompliance were identified.
809 050