IR 05000275/1981004
| ML17083A854 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/25/1981 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17083A853 | List: |
| References | |
| 50-275-81-04, 50-275-81-4, 50-323-81-04, 50-323-81-4, NUDOCS 8104300131 | |
| Download: ML17083A854 (12) | |
Text
U. S.'UCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT t
50-275/81-04 Report No 50-323/81-04 Do'eke t No.
50-275/50-323
REGION V
Lj.cense No CPPR-39
~
CPPR
Sageguards Group Pacific Gas and Electric Company P. 0.
Box 7442 San Francisco, Califor nia 94106 Facility Name Diablo Canyon Units 1 and
Ins ect ion at Diabl o Canyon Site, San Luis Obi spo County, Cal ifornia Ins ect fon conducted March 10-13>
1981 Inspectors:
I D. F. Kirsch, Reactor ec Date Signed I ~ 'k Date Signed Approved By:
D. F. Kirsch, Acting Chi Re tor Projects Section
Reactor Construction Pr 'ects nch Su~ ry:
Date Signed I
~
Date Signed Ins ection durin eriod of March 10-13 1981 Re ort Nos.
50-275 81-04 and
~23 -I Areas Ins ected:
Routine unannounced inspection by a regional based inspector o
construct>on and modification activities including: licensee action on previous inspection findings and 50.55(e)
items; and the reactor vessel vent and level indicating system procedure review, work observation and record review.
The inspection involved 21 inspector-hours on site by one NRC inspector.
.'esults:
No items of noncompliance or deviations wer e identified.
@~@(r @00l8/
3 ~
3 Ih 4 I
~
~
h RV Form 219 {2)
DETAILS 1.
Individuals Contacted a,
Pacific Gas and Electric Compan PG&E)
M. R. Tressler, Supervisory Project Control Engineer J.
B. Hoch, Project Engineer
- R. D. Etzler, Project Superintendent
- D. A. Rockwell, Resident Electrical Engineer
- S. J. Foat, Coordinating gC Engineer N.
E. Leppke, Resident Mechanical Engineer J. Bratten, gC Inspector C. A. Hemstock, Cleanup Crew General Foreman
- M. Dobrzensky, gA Engineer L. Narkum, Instrument Technician Various other crafts and gC personnel.
b.
Pullman Power Products Kello
)
R. Mark, NDE Examiner c.
H. P.
Foie Com an Foie
)
V: Tenneyson, gA Manager B. Price, NDE Examiner
Denotes Exit Interview Attendees.
2.
Site Tour Upon arrival on site the inspector toured the facility to observe in-process and completed work activities to ascertain general compliance with regulatory requirements, codes, standards and procedures.
Activities examined included:
(a) technical support center construction activities; (b) post-accident coolant sampling facility construction activities; (c electrical panel storage conditions for post accident monitoring and sampling facility and (d) control room pressurization system electrical terminations (approximately 30), redundant circuit separation, electrical and mechanical support installation and support welding.
Discussions with licensee personnel indicated that the licensee anticipates the completion of engineering reviews of all as-built support details, relating to seismic design sufficiency, by April 15, 1981.
Ho items of noncompliance or deviations were identifie.
Licensee Action on 50.55 e
Items a ~
Closed Insulation failure of electrical cables routed to the nest 1 inta e structure See a so IE Ins ect on Re ort Nos. 50-275 8 -1 an The licensee's final report on the subject deficiency was submitted by letter dated December 12, 1980.
The Unit 1 deficiency was documented by nonconformance report no.
DC1-80-RE-003-and the attendant resolution and corrective actions had been verified completed by gC.
The licensee had established and approved procedures to inspect the damaged electrical conduit, repair/replace the damaged conduit, and repair damaged conduit and cabling in underground runs to the intake structure.
Engineering approvals of repairs were well documented.
The Unit 2 conduits were repaired by similar methods used on Unit 1.
The installation of concrete cases and encasements were complete and backfill was in progress.
The completion of wire pulls for the Unit 2 intake structure will be completed when new cabling is received.
b.
The inspector had no further questions and this item is closed.
Closed for Unit 1 Crackin in heav ru ture restraint weldments See a so IE Ins ect on Re orts Hos.
50-
9-1 9-1 9-2 an The licensee's final report on this matter was submitted by letter dated December 9, 1980 and addressed the Unit 1 corrective actions noting that a separate report would be submitted for Unit 2 at a later date.
The licensee indicated that repairs to the Unit 2 pipe rupture restraint weldments was about 60'A complete.
The inspector's examination of NCR Nos.
DC1-79-RM-010 and DC2-79-RN-011 and discussions with the licensee's Senior Civil Engineer responsible for the resolution of this deficiency indicated that all Unit 1 repair work had been completed and all documentation of NDE and repairs had been verified.
The Unit 1 final report adequately reflected the work accomplished.
c.
(Closed for Unit 1 Discre ant Pi e to stanchion welds See also IE Ins ect>on Re ort o.
-
-1 The Unit 1 portion of nonconformance report no.
DCO-78-RM-002 was closed and the verification of resolution and corrective actions had been completed by the licensee.
Nonconformance report (NCR) no.
DC2-79-RN-012 was issued to document the situation and resolution for Unit The NCR documents that all Unit 1 field installed pipe/stanchion full penetration welds were repaired except for four inaccessible hangers (nos.
99/120A, 99/121A, each Code Class C; 63/15A and 63/2A, each Code Class B).
Ultrasonic examination of the welds on these four hangers, performed by the licensee's Department of Engineering Research, revealed no defects and evaluation by the Mechanical and Nuclear Engineering Department, determined these supports to be acceptable as is.
All other applicable Unit 1 Code Class A,
B and C supports had been repaired.
The licensee stated that the final report for Unit 1 would be submitted in the near future.
This item is closed for Unit 1 pending receipt and evaluation of the licensee's final report.
4.
Licensee Action on Previousl Identified Items (Closed 275 80-16-01 Followup Item: Cleanu crew trainin and the means of contro sn an accom ss )n c eanu crew wor nee stren t enon The inspector examined the log of cleanup crew training activities conducted since December, 1980 and observed that several training sessions covering various gC and work activities had been conducted for cleanup crew crafts and supervision.
The licensee stated that the cleanup crew at Diablo Canyon was being disbanded, with work turned over to on-site contractors, to support necessary work at other PGSE generation facilities.
This item is closed.
5.
Unit 1 Modifications Related to TMI:
Reactor Vessel Vent Pi in and Reactor Vesse Hater Leve Indication S stem.
The inspector examined the licensee's activities affecting the installation of the Unit 1 reactor vessel vent and level indicating system.
The vent piping work and attachments to the reactor coolant pressure boundary were being performed by Pullman Power Products and the instrument tubing installations were being performed by H.
P. Foley Company in accordance with Hestinghouse design and design change orders issued by PG&E Engineering.
The following aspects of the installation were examined for compliance with licensee procedures, drawings and industry codes and standards:
Design Change Orders DCO-'-E-597, E-M-809 Ten drawings and details effecting pipe and tubing installation Foley Procedure (CPM-1, "Installation of Stainless Steel Tubing and Fittings" Foley Procedure (CPM-16, "Drying, Filling and Testing Barton Bellows Sensor Type Capillary System"
Receipt inspection reports for six level transmitters, six hydraulic isolators, 3/16" stainless steel tubing and weld coupling adapters Naterial certifications for 3/4" schedule 160 stainless steel pipe Visual weld examination on nine field welds for the reactor vent piping and observation of liquid penetrant examination on two of those welds Welding field process travelers, liquid penetrant reports, and weld rod requisitions for seven of the above completed field U>elds Welder and NDE examiner qualification documentation for one Pullman welder and one NDE examiner and one Foley NDE examiner Fit up and completed tack weld on the RVLIS fitting to loop 3 hot leg reactor coolant pipe Liquid penetrant examination reports for eight Foley performed tubing welds on the RYLIS Foley installed Unistrut tubing housings for visual weld quality, tube support clip spacing, Unistrut channel support spacing, support installation and tubing clip configuration.
The following concerns were identified and communicated to responsible licensee personnel:
a ~
b.
C.
The Foley system only provides for a final inspection after all tubing installation work is completed and does not provide for in-process inspections of tubing Unistrut channels, welding, support installations or tube support, clip installation.
Although all Foley work had not been completed, the licensee took immediate action to evaluate and resolve the inspector's concern.
Although Foley's final inspection of the RVLIS tubing installation had not been performed the following problems were identified to licensee management:
(1)
Unistrut channel supports - several shell type concrete anchor bolts were observed to contain two washers with some washers being free to move, indicative of'remature bottoming of the shell anchor bolt.
(2)
Welding - several Unistrut channel/channel welds and channel/
support steel welds were unacceptable and several welds had been painted, necessitating paint removal prior to visual inspection.
(3)
The tube clip detail did not specify weld details or weld acceptance criteria (i.e., weld length and size requirements).
The licensee took immediate action to obtain engineering guidance on tube clip weld requirements
.
The inspector questioned the advisability of using Swagelok fittings in those portions of the RVLIS exposed to contaminated reactor coolant at reactor coolant system pressure.
The licensee stated. that the use of such fittings would be evaluated and resolved by Engineerin d; The Foley procedure gCPfl-1 did not contain installation guidance or inspection criteria for Swaglok fittings.
The licensee took immediate action to revise the Foley procedure to specify appropriate installation and acceptance criteria.
The licensee's resolution of the above concerns and questions will be examined during a future inspection.
(275/81-04-01)
The inspector observed about 12 arc strikes on the loop 1-3 hot leg pipe which obviously came about in the process of performing the tack weld fitting the RVLIS fitting to the loop pipe.
The Kellogg gC had not yet examined the tack weld and these conditions were identified to Kellogg (}C and the licensee.
Immediate corrective action'as taken to remove the arc strikes and perform surface examination and wall thickness verifications in the areas affected by the arc strike removal operation.
The inspector had no further questions in this area.
No items of noncompliance or deviations were identified.
6.
Exit Interview The inspector met with licensee representatives denoted in paragraph
at the conclusion of the inspection on Narch 13, 1981 and summarized the inspection scope and finding \\
I