IR 05000361/1979007
| ML13309A695 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/26/1979 |
| From: | Haist D, Haynes R, Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13309A693 | List: |
| References | |
| 50-361-79-07, 50-361-79-7, 50-362-79-07, 50-362-79-7, NUDOCS 7907110725 | |
| Download: ML13309A695 (8) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50-361/79-07
'-Report N /79-07 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
'Fatienity Name:
San Onofre Uni.ts 2 and 3 Inspection at:
Construction Site, San Diego County, California inspection conducted:
February 1-28, 1979 Inppct ors:
Ad, Awe-A
.R 4 00
______L79_
R. J. Pate, R sident Re ctor Inspector Date Signed D. P. aist, Reactor Inspector Date Signed Date Signed Approved By:
__
R. C. Haynes ief, Projects Section, Reactor bate Signed Construction and Engineering Support Branch Summary:
Inspections on February 1-28, 1979 (Report Nos. 50-361/79-07 and 50-362/79-07)
Areas Inspected: Routine, unannounced inspections by regionAl and resident inspectors of construction activities including:
pipe storage, fitup and welding; piping post weld heat treatment; reactor pressure vessel and internals protection; safety related component storage; safety related instrumentation; electrical components and systems; and followup of licensee actions on previous inspection findings. The inspection involved 101 inspector-hours onsite by two NRC inspector Results: Of the five areas inspected, two items of noncompliance were identifie s RV Form 219 (2)
DETAILS 1. Individuals Contacted a. Southern California Edison Company (SCE)
=L. L. Hamlin, Project Manager
=H. B. Ray, Manager, Quality Assurance
- R. R., Hart, Construction Superintendent
=D. B. Schone, Lead Engineering Site Representative
- =+P. P. Croy, Site Quality Assurance/Quality Control Supervisor
- L. L. Seyler, Project.Quality Assurance Supervisor
- P. R. King, Quality Assurance Engineer J. J. Pantaleo, Quality Assurance Manager
- =W. F. Rossfeld, Quality Assurance Engineer
=L. D. Tipton, Engineering Site Representative F. Frick Quality Assurance Engineer
=D. E. Nunn, Engineering Supervisor
+W. M. Schwab, Construction Engineer
+3. K. Huey, Quality Assurance Engineer b. Bechtel Power Corporation (Bechtel)
- =+C. A. Blum, Quality Control Manager
- R. H. Cutler, Project Field Engineer
- + E. Geiger, Project Field Quality Assurance Supervisor J. L. Ruud, Lead Quality Assurance Engineer
- =+J. R. Caldwell, Project Quality Assurance Supervisor
- =. E. Bashore, Division Quality Assurance Manager
- +R. W. Welcher, Project Quality Assurance Engineer In addition, construction craftsmen, engineers and foremen were contacted during the inspection *Denotes attendees at management meeting on February 2, 197 =Denotes attendees at management meeting on February 9, 197 +Denotes attendees at management meeting on February 23, 197.
Construction Status The licensee reported that site construction work is 65% complete as of March 1, 197.
Licensee Action on Previous Inspection Findings The inspector examined the corrective action taken by the licensee on the following outstanding item a. (Open) Follow-up Item (50-361/78-17/01): The adequacy of plant procedures to provide for protection of items stored in-place was addressed in IE Inspection Report No. 50-361/78-13. Portions of this item were resolved as reported in report 50-361/78-17/0 However, a complete review of the plant procedures had not been mad The inspector reviewed the plant procedure and the results of the review were discussed with the licensee on February 15, 1979. All the procedu-res appeared to satisfy the storage and maintenance re quirements;of ANSI N45.2.2-1972, except that there were no provisions for. documented periodic inspections of storage conditions for items stored in Zone V Housekeeping Areas. This item remains open pend ing resolution of this procedural omissio (Closed) Unresolved Item (50-361/79-05/01): The storage of the Fin-Fan Radiator fan motor was not in accordance with the vendor manua The vendor's manual, as revised by telephone conversation with Bechtel Field Engineering personnel, required the fan motors to be rotated every 30 days. The motor shafts were not rotated as required because the supplemental maintenance requirements were not issued for over a month after the equipment arrived. Bechtel issued a nonconformance report and had the motor vendor inspect the motors. The vendor deter mined that the motors were in satisfactory condition. The motors were stored in a covered area and the motor heaters energized. All the responsible Field Engineers were instructed to review vendor manuals and to issue supplemental vendor maintenance.requirements on a more timely basis to prevent recurrence of this condition. The inspector found the corrective action satisfactor (Closed) Unresolved Item (50-362/78-13/01): Post weld heat treatment (PWHT) of welds is a special process and the procedure must be quali fied. The procedure qualification.records-were not available for revie Bechtel welding personnel stated that the records were not formal qualification records, but provided evidence that the process was in control. The records were provided for the inspector's review on February 2, 1979, in the form of a report titled "Report on the Tem perature Uniformity of Quartz Lamp Post Weld Heat Treatments, January, 1979."
The data provided indicated that the temperature differential from the outside to the inside of the pipe during PWHT with quartz lights could exceed 1000F for pipes with 3 inches or greater wall thick ness. Selected PWHT records for both Unit 2 and 3 for pipe with wall thickness 3 inches or greater were reviewe The inspector noted that
-3 the maximum recorded hold temp8rature on the outside of the pipe was generally in the range of 1130 F to 11600 F. The following are examples of records reviewe Weld Wall Max Time Ab8ve Line N Thickness Hold Tem F S3-1201-ML-005, Sh. 1 B
3" 1150 F 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> S3-1201-ML-001 A
4 1/2" 1130 F 4 hrs 15 min Based on the above, the inspector found that the process qualification data did not demonstrate that the inside wall temperature for pipes with wall thickness of 3 inches or greater met the design requirement i.e., the PWHT temperature range specified in the ASME Boiler and Pressure Vessel Code,Section III, Paragraph NB-462 Failure. to qualify the PWHT procedure before use is an item of noncompliance. (50-361/79-07/01 and 50-362/79-07-01)
4. Reactor Vessel and Internals Storage Site activities for storage of the Unit 2 and 3 reactor pressure vessel and internals were observed. The constructor was controlling access to the equipment and maintaining protective covers as required by the construction procedure No items of noncompliance or deviations were identifie. Reactor Coolant Pressure Boundary and Safety Related Piping The piping related activities listed below were observed to ascertain compliance with the applicable construction procedure Activity System Identification N Pipe Storage Reactor Coolant 2-RC-054-IC, Sh. 1 2-RC-054-IE, Sh. 1 2-RC-054-IA, Sh. I 2-RC-054-IH, Sh. 1 Pipe Fitup Safety Related S2-2420-056 S2-2420-057 Welding Safety Related S2-1203-ML-162 Welding Safety Related 2-CH-052-7 Welding Reactor Coolant S3-1201-ML-005, Sh. 1 No items of noncompliance or deviations were identifie. Safety Related Equipment The storage requirements and storage conditions for Unit 2 steam generators were reviewe The inspector verified that the vendor storage requirement were being met. The inside of the north steam generator was inspected and found to be relatively free of corrosion. The Combustion Engineering repre sentative stated that the condition of the steam generator was acceptabl.
Instrumentation -
Components and Systems a. Observation of Work and Work Activities The inspector visually examined partially completed work on instruments for the systems indicated below to verify compliance with selected licensee installation drawings and procedure No itemsiof noncompliance or deviations were identifie (1) Reactor Protection System (a) Pressurizer Pressure -
Instrumentation No. 2PT-0101-4 (Channel D) transmitter mounting and locatio (b) SteamGeneratorWater Level - Instrument No. 2LT-1113-3 (Channel D) transmitter mountin (c) Steam Generator Pressure - Instrument No. 2PT-1013-1 (Channel A) and No. 2PT-1023-4 (Channel B) transmitter mounting and locatio (2) Engineered Safety Features Actuation Signals (a) Pressurizer Level'- Instrument No. 2LT-0110-T (Channel A)
transmitter mounting and locatio (b) Containment Radiation - Instrument No. 2RT-7860-3 (Channel C)
element and transmitter mounting and locatio (c) Fuel Handling Area Radiation -
Instrument No. RE-7858-1 (Channel A) element and transmitter mounting and locatio (d) Refueling Water Storage Tank Level' - Instrument No. 2LT-305-4 (Channel D) transmitter functional check, mounting and locatio (3) Normal Plant Control Signals (Safety Significance)
(a)
Auxiliary Feedwater Flow to Steam Generator E-088 - Instrument No. 2FIT-4720-1 - transmitter functional chec (b) High Pressure Safety Injection No. 2 Pressure -
Instrument No. 2PT-0309, transmitter functional check, mounting, and locatio (c) Feedwater Flow to Steam Generator E-089-Instrument N FT-1111, transmitter functional chec (d) Main Steam Flow from Steam Generator E-089 -
Instrument No. 2FT-1011, transmitter functional chec The inspector noted that, although not yet installed, the instrument tubing from sensor to 2LT-1113-2 and from sensor to 2LT-1113-4 as shown on drawing FDG-J-559, Sh. 3, Rev. 1, appears to violate the requirement for 18-inch separation between channels. This condi tion also appears for tubing from sensor to 2LT-0110-1 and from sensor to 2PT-0104-2 as. shown on drawing FGD-J559, Sh. 2, Rev. The Bechtel instrument engineer is aware of the condition and stated that a separation. review will take place after tubing installation and protective channels will be installed over instrument tubing that does not meet the minimum separation dis tance prior to final acceptance. This item will be re-examined in a subsequent inspectio (50-361/79-07-02)
b. Review of Quality Records Quality records for the instruments observed in item a. above were examined andappeared to adequately reflect the status of instrument installation as required by licensee procedure The records examined included the Construction Inspection Data Reports for concrete anchors and final instrument installation, pressure test records, pressure gauge calibration records, water chemical content certifications and functional test record The inspector noted that instrument tubing is being correctly hydrotested to a minimum test pressure of 1.5 times design pres sur The hydrotest pressure commonly used is 3750 psig, however, pressure gauge calibration is being performed at 3700 psig which conflicts with the gauge calibration requirement to calibrate to the specific test pressure using a standard dead weight tester or calibrated master gauge. Bechtel representatives stated that the pressure gauges are scaled from 0 - 10000 psig at 100 psig incre ments and that the practice is to record 3700 psig although exceed ing it during the calibration. 'Bechtel stated that calibrations will be done at 3800 psig to resolve this conflict, and has initi ated a nonconformance report to document the acceptance of the completed test. The inspector had no further questions on this matte.
Electrical - Components and Systems a. Observations of Work and Work Activities The inspector observed the termination of the following nuclear safety related cables for conformance with selected installation drawing and QC procedure requirement (1) Changes. to control jumpers in diesel generator 2G003 protective relaying and metering panel 2A06 in accordance with Field Engineering Work Request No. 52 (2) Control cable in ESF Actuation System Aux Cabinet B-2L035, cable scheme.No, 2DRLO350 (3) 480 V power cable from load center breaker 2B0G14 to MCC 2BZ, cable scheme No. 2BB0614P (4) Control cables at containment penetration 2BC4RP96, cable scheme Nos. 2BRCPlO3 and 2BRCP110 The inspector noted that item 1 of the Construction Inspection Date Report (CIDR), verification of termination card information had not been completed by the Construction Field Engineer for cable scheme Nos. 2DRLO350A, B, C and D. Also, the quality class had not been assigned to the CIDR by the CFE. WPP/QCI No. 605, Rev. 8, Para graph 7.1.1 requires this information to be verified and added to the CIDR before termination is allowed. Bechtel initiated a Corrective Action Request (CAR No. F596) recommending an investigation of CIDRs issued. An investigation of 525 correction cards revealed no cards in violation and directions were issued to all CFE toadhereto WPP/QCI No. 605. This item is considered to be unresolved pending the in spector's review of results of the corrective action reques (50-361/79-07/03)
b. Review of Quality Records The inspector reveiwed the following records associated with the cabl terminations observed in a. above for conformance with selected QC procedure requirement (1) Electrician certification records (2) Crimp tool calibration records (3)
Crimp tool calibration gauge records (4) Drawing control
-7 The inspector noted that calibration records are not being maintained for the AMP Hydraulic foot pump No. EC-206, used for crimping large termination lugs. The AMP vendor manual for hydraulic foot pump model No. 69325 indicates that the pressure relief valve setting must be reached to effect a proper crimp. The vendor manual also indicates that the pressure relief valve setting of 8000-8400 psig should be veri fied once per month and provides instruction for performing the verifica tion test. The failure to follow vendor's recommendation for verification of hydraulic pump performance is considered to be an item of noncomplianc (50-361/79-07-04)
9. 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 supervision and quality control inspectors at the work areas, housekeeping and preservation of equipmen No items of noncompliance or deviations were identifie.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during this inspection is discussed in Paragraph.
Management Interview The inspector met with the licensee representatives (denoted in Paragraph 1)
on February 2, 9 and 23, 1979. The scope of the inspections and inspector's findings as noted in this report were discussed. The licensee representatives had no additional comments.