IR 05000361/1978017
| ML13309A599 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/28/1978 |
| From: | Haynes R, Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13309A598 | List: |
| References | |
| 50-361-78-17, 50-362-78-13, NUDOCS 7812280224 | |
| Download: ML13309A599 (7) | |
Text
U. S. NUCLEAR REGULATORY COMM1ISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50-361/78-17 Report N /78-13 50-361 CPPR-97 Docket N License N CPPR-98 Safeguards Group Licensee:
Southern California Edison Company P. 0. Box 800 -
2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Units 2 and 3 Inspection at:
Construction Site, San Diego County, California Inspection Conducted:
October 2-31, 1978 Inspectors:
//2-9/79 R. J. Pate, Resident ector Inspector Date'Signed Date Signed Approved By:
l/
9/
R. C. Haynes, w4'ef, Projects Section, Reactor Date Signed Construction and Engineering Support Branch Summary:
Inspections on October 2-6 and 16-31, 1978 (Report Nos. 50-361/78-17 and 50-362/78-13)
Areas Inspected: Routine, unannounced inspections by the resident inspector of construction activities including: piping installation, piping welding, piping supports, polar crane supports, reactor pressure vessel and internals protection, followup of licensee actions on previous inspection findings and general work in progress. The inspection involved 31 inspector-hours onsite by one NRC inspecto Results:
Of the seven areas inspected, no items of noncompliance or deviations were identifie I8E1228 0r
IE:V Form 219 (2)
DETAILS Individuals Contacted a. Southern California Edison Company (SCE)
3,2H. B. Ray, Manager, Quality Assurance 2R. R. Hart, Construction Superintendent 3. B. Schone, Lead Engineering Site Representative 3,2,1P. A. Croy, Site QA/QC Supervisor 2,1L. L. Segler, Project QA Supervisor L. D. Hamlin, Project Manager 3J. J. Pantaleo, QA Engineer W. F. Rossfeld, QA Engineer M. Rodin, QA Engineer R. Frick, QA Engineer F. Pimentel, QA Engineer b. Bechtel Power Corporation (Bechtel)
3,2,1W. D. Nichols, Project Engineer 3,211C. A. Blum, Quality Control Manager 3,2,1R *H. Cutler, Project Field Engineer J. E. Geiger, Project Field QA Supervisor 3,2 1J. Hosmer, Assistant Project Engineer 2 2 R. Caldwell, Project QA Supervisor 1. JE. Bashore, Division QA Manager B. M. McCullough, Field Construction Manager In addition, construction craftsmen, engineers and foremen were contacted during the inspection Denotes attendees at management meeting on 10/6/7 Denotes attendees at management meeting on 10/20/7 Denotes attendees at management meeting on 10/27/7 Construction Status The licensee reported that site construction work is 61% complete as of October 27, 1978. The licensee's project management person nel estimate that the construction effort is split 60%/40% between Units 2 and.
Licensee Action on Previous Inspection Findings The inspector examined those corrective actions taken by the licensee on the following previously noted enforcement or un resolved item a. (Closed) Noncompliance (50-362/78-05): An eight-inch check valve installed in a vertical line in the Safety Injection System was found to be improperly designed in that the valve could not perform its required function when installed in the vertical positio The licensee has taken corrective action to assure no other SONGS Units' 2 and 3 valves have a similar proble (See Report No. 50-362/78-09.) The four affected valves have been corrected and the work was verified by the licensee's QA personne The inspector had no further question b. (Closed) Unresolved Item (50-361/78-08): Dye penetrant developer remaining on weld. The dye penetrant was left on the weld as an aid for grindin (See Report No. 50-361/78-12.)
The control of nondestructive test consumables by other than QA/QC personnel raised a question of the control of these items by all the site contractors. To provide better control of test consumables like dye penetrant developer, all site contractors were required to follow the requirements of specification CS-GP-208 which requires certification or user's.test, as applic able, and lists the limitations on the use of each consumabl The use of consumables by all site contractors in accordance with CS-GP-208 will assure that safety related systems and components will not be adversely affecte c. (Closed) Unresolved Item (50-361/78-13): The Shutdown Heat Exchange was installed with no provisions for internal moisture contro The heat exchanger is clad with stainless steel and no moisture control is required by ANSI-N45.2 or the plant storage procedure The inspector had no further questions on this matte d. (Open) Unresolved Item (50-361/78-13): The adequacy of plant procedures for items stored in-place was questioned by the NRC inspector due to the apparent storage inadequacies of the shut down heat exchangers, high pressure safety injection pump and Unit 3 north steam generato As noted in Item 3.c, above, the storage of the shutdown heat exchanger was in accordance with plant procedures. In a meet ing with the licensee's management personnel, the inspector was advised that the present storage procedures were believed to be adequate. The collection of debris on and around the HPSI pump and the absence of a cover on the steam generator cold leg nozzle were isolated instances of failure to follow procedures. In both cases, the problem was corrected imme diately and there was no detrimental affect on the equipmen Corrective action requests (CAR) were initiated and will be completed in accordance with plant procedures. The inspector had no additional questions on these specific items, but noted that all the appropriate plant procedures (a list was provided by the licensee) would be reviewed in a subsequent inspectio (50-361/78-17/01)
4. Installation of Temporary Pipe Supports An analysis performed by Bechtel indicated that schedule 10 pipe could be used for temporary support of other heavier wall pipe over typical spans of 10 feet and not be damaged when supporting pipes of equal diameter. However, relatively small (4 inch) sche dule 10 pipe could not be used to support large diameter pipe (16 inch). To avoid confusion, Bechtel instructed the construction personnel to use equal diameter pipe or larger for temporary sup port of pipe spools, unless the schedule, of the supporting pipe could be positively identified as heavier than schedule 10. The inspector had no additional questions, but noted that implementa tion of the instructions for temporary pipe support will be re viewed in a subsequent inspectio (50-361/78-17/02) Polar Crane Support The inspector observed that the polar crane supports for Unit 2 were constructed with double slotted holes (both connected members had slotted holes at the connection). Use of double slotted holes is not permitted by the licensee's construction specification 205-1 for shear connections using high strength bolts. However, the 11 censee advised that the connection in question was a pure tension connection for which double slotted holes were permitted by their specification. The inspector had no further question. Observation of Construction Activities a. Reactor Coolant Pressure Boundary and Safety Related Piping The following piping activities were observe (1,)
Piping Storag The storage of the pipe at the off-site laydown area was in accordance with procedure WPP/QCI 008, Rev. Pipe storage at the laydown area north of Unit 2 contain ment building was generally in accordance with procedure WPP/QC1 008. The inspector observed several spools of reactor coolant system, component cooling water system and safety injection system pipe which were not fully stored on cribbing. The licensee's immediate corrective action was to place the pipe spools on the cribbing and initiate a Corrective Action Request (CAR)
to prevent re currenc The inspector had no further questions at that time, but stated that this area would be reexamined during a subsequent inspection. (50-361/78-17/03)
(2) Pipe Handling Pipe handling was performed in accordance with procedure WPP/QCI 013, Rev. (3) Post Weld Heat Treat Post weld heat treating operations were in progress on the Unit 3 south steam generator cold leg nozzle-to-elbow weld and weld CA on the Unit 3 main steam line (ref: Draw ing S3-1301-ML-001, Sheet 3).
The operations were conducted in accordance with procedure WPP/QCI 009, Rev. The inspector noted that some of the activities performed by the post weld heat treat operators were not verified by an independent inspection. For example, procedure WPP/QCI 009, Rev. 0, did not require the QC inspector to verify the location of the thermocouple used to provide input to the heat treat recorder. The scope of QC inspec tions for PWHT operations will be examined further during a subsequent inspectio (50-362/78-13/01)
(4) Pipe Installation and Fitup Installation of mainsteam line spool S2-1301-ML-583 and reactor coolant spool S3-1201-ML-007 were in progres No departures from procedure WPP/QCI 400, Rev. 8, were observed by the inspecto (5) Grinding Grinding of safety injection tank nozzle-to-pipe weld (pipe no. S3-1204-005-001) for preservice inspection was in progress. Procedure CS-P204 was being followed. Also, grinding on the Unit 3 reactor pressure vessel cold leg weld A (pipe no. S3-1201-ML-007) was in progress. This operation was being performed in accordance with noncon formance report (NCR) N-26 No departures from procedural requirements were observe b. Reactor Pressure Vessel Protection The Unit 2 and 3 reactor pressure vessels (RPV) have both been set in place in the containment buildings. The follow ing was observe (1) The procedures for protection of the installed RPVs (WPP/QCI 009, Rev. 5 and 505, Rev. 0) were being followe (2) All openings (top and nozzles) which have not been connected to permanent piping were covered. Where piping had been connected, the open end of the pipe was covered but for one exception at Unit 3. Namely, an air jet eductor had been installed at each coolant loop cold leg safety injection pipe connection to provide ventilation to workers performing welding and grinding operations in the cold leg piping. These eductors provided an open path approximately 6 inches in diameter to the RPV which was not covered during the second shift. The absence of covers was discussed with the licensee and the constructor and they stated that the opening would be covered during periods when work was not in progress. This area will be reexamined during a subsequent inspection. (50-362/78-13/02)
(3) The work platforms and scaffolding inside the vessels were treated with fire retardant chemicals or covered with nonflammable materials, except for the hand rails in Unit 3 RPV. The hand rail in Unit 3 RPV did not have a covering of protective material or paint and did not appear to have been treated (pressure impregnated)
with fire retardant chemicals. This is an unresolved ite (50-362/78-13/03)
(4) Access control was being maintained for each RP An attendant was on duty for both vessel *
-6 c. Reactor Vessel Internals The reactor vessel internals for Unit 2 were being stored in a controlled access area with an attendant on dut The internals for Unit 3 were stored in the Unit 3 contain ment with a protective cover. The storage requirements of WPP/QCI 009, Rev. 5, and Combustion Engineering Proce dure CEND-353 were being followe d. Reactor Coolant Pressure Boundry Piping Weld The inspector observed the welding of pump nozzle-to-cold leg pipe weld A (pipe no. S3-1201-ML-007) for Unit 3. Automatic welding machines were being used. The Field Welding Check List (WR-5) and Filler Metal Withdrawal (WR-6) were reviewed and were completed in accordance with WPP/QCI 200, Rev. 1 The welding equipment was in good condition and the weld procedures were being followe e. Safety Related Piping Weld The welding operations on weld BD for mainsteam line-to containment penetration (pipe no. S2-1301-ML-002, Sheet 2)
for Unit 2 were observed. The WR-5 and WR-6 were reviewe The weld procedure Pl-(G2)-T-I-0(ITP), Rev. 2, for the root and procedure P1-a-Lh (CVN), Rev. 0, for the remainder of the weld were being followed. The weld equipment appeared to be in good condition and the requirements of procedure WPP/QCI 200, Rev. 10, were being followe. Plant Tour The inspector toured both Units 2 and 3 several times each week during this inspection report period. Particular attention was directed to observing work in progress and availability of super vision and quality control inspectors at the work areas, house keeping and preservation of equipmen No items of noncompliance or deviations were identifie Management Interview The inspector met with the licensee representatives (denoted in Paragraph 1) on October 6, 20, and 27, 1978. The scope of the in spections and inspector's findings as noted in this report were dis cussed. The licensee representatives had no additional comment I0