IR 05000304/1979004
| ML19261E327 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/11/1979 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19261E322 | List: |
| References | |
| 50-304-79-04, 50-304-79-4, NUDOCS 7907050553 | |
| Download: ML19261E327 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-304/79-04 Docket No. 50-304 License No. DPR-48 Licensee:
Commonwealth Edison Company P.
O.
Box 767 Chicago, IL 60690 Facility Name:
Zic. :4uclear Generating Station, Unit 2 Inspection At:
Zion Site, Zion, IL Inspection Conducted:
March 12-13 and April 3-4, 1979
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Inspector:
W.
J. Key df/ /
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W Approved By:
D. H. Danielson, Chief d /// 2 f Engineering Support Section 2 Inspection Summarv Inspection on March 12-13_and April 3-4, 1979 (Report No. 50-304/79-04)
Areas Inspected: Review of ISI program, procedures and ammendment; observation of work and work activities; data review and evaluation.
The inspection involved a total of 32 inspector-hours onsite by one NRC inspector.
Results: Of the four areas inspected, no apparent items of noncom-pliance were identified in three areas; one apprent item of noncor-pliance was identified in c - area (infraction - failure to provide certified calibration standreds for checkir.5 measuring equipment -
Paragraph 3.b).
M 7907050563 2.9 ) $107
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DETAILS Persons Contacted Commonwealth Edison Company (CECO)
- N.
E. Wandke, Station Superintendent
- L.
G.
Soth, Ass stant Superintendent
- B.
Shanon, ISI Coordinator
- C.
G. Silich, Assistant ISI Coordinator
- J.
Mariany, Technical Staff Supervisor
- R.
Rostkowski, Quality Assurance Engineer Westinghouse Electric Company (W)
- B.
J.
Lefebvre, NSD Senior Engineer, Level III
- Masaaki Kina, NSD Engineer (Brazil)
- Denotes those present at the exit interview.
Functional or Program Areas InErected 1.
Inservice Inspection (ISI) Program Review The inspector reviewed the ISI program for l' nit 2 and determined that:
a.
The program had been approved by the licensee.
b.
QA plans and procedures have been written, reviewed, approved and issued.
c.
The organizational structure specifies the qualifications, indoctrination and training of QA personnel responsible for ISI audits and inspection activities.
d.
The program includes examination reports, acceptance criteria, identification of components and systems to be examined during this outage.
c.
The program includes a description of the areas to be examined in accordance with Technical Specification 4.3 and ASME Section XI, 1974 Edition including Summer 1975 Addeqda.
292 30D-2-
f.
Items to be examined are as follows:
(1) Reactor Vessel Bl.2, weld No. 1 from 1" to 2" down from veld No. 5, sketch No. 1-1300.
Bl.2, weld No. 5 from 6.84" to 18.0" CW from stud hole No. 1, sketch No. 1-1300.
Bl.8, Closure head studs and nuts No. 19 to No. 36, sketch No. 1-1400.
Bl.ll, Conceal bolting, 6 bolts at penetration No. 75, sketch No. 1-1300.
(2) Pressurizer B2.1, Circunferential weld No. 1 through No. 5, a length of 5", sketch No. 1-2100.
B2.2, Nozzle to vessel weld No. 13 and 14, sketch No.
1-2100.
B2.4, Safe end weld, examine 1 DM (100?.), sketch No.
1-4504 B2.11, Bolting No. 5 through 12, sketch No. 1-2100.
(3) Steam Generator B3.1, Tubesheet welds 1-1, 2-1, 3-1 and 4-1, a length of 7.5",
sketch No. 1-3100.
B3.ll, Bolting No. S through 8 and 21 through 24, sketch No. 1-3100.
(4) Dismillar Metal Welds B4.1, Safe end weld No. 5 DM and 6 DM (100%), sketch No. 1-4300.
(5) Piping Systems B4.5, RC pipe welds No. 3, 4, 7 and 8 * sketch No. 1-4300.
2h1 bIf-3-
B4.5, 10" butt weld No. 11 through 16, sketch No. 1-4201.
(6)
Integrally Welded Supports B4.5, 8" butt weld No. 15 through 19, sketch No. 1-4501.
B4.5, 6" butt weld No. 2 through 4, sketch No. 1-4502.
B4. 5, 4" but t weld No. 2, 7 and 8, sketch No. 1-4505.
(7)
Socket Welds B4.8, weld No. 2 through 6, sketch No. 1-4307.
B4.8, weld No. 1 through 6, sketch.
1-4307.
(8) Welded Supports B4.9, support No. H5, sketch No. 1-4102.
B4.9, support No. H1, sketch No. 1-4207.
(9)
Support Components B4.10, support No. H1, H2, H6 through H8 and H10 through H12.
(10) Pressure Retaining Bolting B4.12, Flange No. 1, sketch No. 1-4203.
B4.12, Flange No. 1, 2 and 3, sketch No. 1-4305.
(11) Valve Pressure Boundary B6.5, Support Component No. H1, sketch No. 1-4201.
B6.9, Bonnet Bolting, 895eC, sketch No. 1-6100.
g.
ASME Section XI, Relief Requested The licensee has requested relief from examinations in the following areas:
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Class I Table IWB 2600 Table IWB 2500 (1)
Bl.2 B-B Lower Head Ring to Disc, Circumferential Weld (2)
B2.2 B-D Nozzle to Vessel Weld (3)
B4.1 B-F Safe End to Pipe Weld (B31.1)
(4)
B4.5 B-J Circumferential ar.d Lcngitudinal Pipe Weld (5)
B4.9 B-1-1 Integrally Welded Supports (6)
B5.1 B-G-1 Reactor Coolant Pump Pressure Retaining Bolting (In Place)
(7)
B5.2 B-G-1 Pressure Retaining Bolting (8)
E5.6 B-L-1 Pump Casing Welds Class II Table IWB 2600 Table IWB 2500 (9)
Cl.1 C-A Regenerative Heat Exchanger, Head to Shell Weld (10) C1.1 C-A Shell to Tube Sheet Weld (11) C1.2 C-B Residual Heat Exchanger (Tube side ~.
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Nozzle to Vessel Welds.
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(12) C1.1 C-A Seal Water Return Filter, Cover Weldment to Shell Weld (13) C1.1 C-A Head to Shell Weld (14) C1. 3 C-C Integrally w'elded Supports (15) C1.1 C-A Seal Water Heat Exchanger, Shell to Flange Weld (3 6) C1.1 C-A Seal Water Injection Filter, Head to Shell Weld (17) Cl.1 C-A Shell to Tubesheet Weld (18) Cl.3 C-C Integrally Welded Supports (19) Cl.4 C-D Pressure Retaining Bolting (20) Cl.1 C-A Reactor Coolant Filter, Cover Weldment to Shell Weld (21) C1.1 C-A Head to Shell Weld (22) C1.3 C-C Integrally Welded Supports (23) C2.1 C-F/C-G Piping System, Circumfer, tisl Butt Welds (24) C2.3 C-F/C-G Branch Pipe to Pipe Welds
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(25) C3.1 C-F Centrifugal Charging Pumps, Pump Casing Welds
- 6-292 304
Class III components ASME Section XI, 1, 2 and 3 valves Valve Section XI ASME Identification IWV 2110 Class (26) 25W-0010 - 6" Check Service C
0011 - Water Diesel Generator Coo'ers (2'/; 2SW-0003 - 20" MOV Service B
0004 - Water to RJFC 0005. roolers 0006 (28) 25W-0007 - 10" MOV Service B
0008 - Water Return from 0009 -
RCFC Coolers 0010 0011 (29) 2CS-016 - 3" Check F zay Additive C
021 to Eductor 026 (30) 2HCV-606 - 10" Butterfly Valve B
607 - RHR Heat Exchanger Outlet (31) 2HCV-618 - 8" A0, Butterfly Valve B
RHR Heat Exchanger By-Pass Pump ASME Identification Class (32) 2VC-006 - Charging (HHSI)
007 - Relief-Vibration Amplitude Measured Parameters (33) 2RH-001 - Residual Heat Removal
002 - Relief-Vibration Amplitude Paramaters
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(34) OCC-003 - Components Cooling
004 - Relief-Inlet Pressure 005 Outlet Pressure 006 Differential Pressarc 007 Flow Rate (35) 2SW-001 - Service Water
002 - h nief-Inlet Pressure 003 Flow Rate Vibration Amplitude (36) 2FW-005 - Auxiliary Feedwater (Motor Driven)
006 - Relief-Vibration Amplitude (37) 2CS-001 - Containment Spray
002 - Relief-Vibration Amplitude 003 (38) 251-003 - Safety Injection
00!- - Relief-Vibration plitude No items of nancompliance or deviations were identified.
2.
Inservice Inspection (ISI) Procedure Review The inspector reviewed the following (W) ISI procedures and amendments for conformance to ASME Code Section XI and V, including the licensee's review and approval.
a.
OPS-NSD-101, Revision 5, Amendment 01 Titled:
Preservice and Inservice Documentation.
b.
PA-10.1, Revision 2 Titled: Training, Qualification and Certification of Personnel in Sondestructive Examination.
c.
ISI-8, Revision 7 Titled: Visual ExTmination Procedure.
d.
NSD-ISI-10, Revision 4, Amendment 01 Titled:
Preservice and Inservice Examination, Manual Ultrasonic Equipment Qualification.
e.
ISl-L', Revision 9, imendment 01
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Titled.
Liquid Penetrant Examination.
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f.
ISI-15, Revision 6, Amendment 01 Titled:
Ultrasonic Examination of Studs, Bolts and Nuts.
g.
ISI-41, Revision 4, Amendment 01 Titled:
Manual Ultrasonic Testing of Reactor Coolant Pump Flywheels, h.
ISI-47, Revision 2, Amendment 4 Titled:
Manual Ultrasonic Examination of Circumferential and Longitudinal Butt Welds in Ferritic Vessels of 2 1/2" Thickness and Greater.
1.
ISI-70, Revision 0 Titled:
Magnetic Particle Examination.
j.
ISI-87, Revision 0 Titled:
Reactor Vessel Internals Drive Rod Assembly Survey.
k.
ISI-88, Revision 0 Titled:
Remote Vessel Examination of Vessel Internals.
1.
ISI-205, Revision 2, Amendment 01 Titled:
Manual Ultrasonic Examination of Full Penetration Circt'mf erential and Longitudinal Welds.
m.
MRS-2.4.2, GEN-19, Revision 0 Titled:
Installation and Removal of Eddy Current Positioning Devices.
n.
MRS-2.4.2, GEN-18, Revision 1, Technical Supplement No. 1, Revision 3 Titled:
Steam Generator Tubing Inspection for Tube Wall Degradation-Detection and Qualification.
o.
MRS-2.2.2, GEN-6, Revision 1 Titled:
Post-Activity Eign-off for Area Cleanliness.
No items of noncompliance or deviations were identified.
3.
Observation of Activities The inspector observed the fol'.owing examinations being performed, exanined calibration blocks and standards, verified examination equipment, personnel certifications and qualificqtions.
f
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a.
Persennel Certifications and Qualifications Westinghouse (W)
R. H. Ingrham II B. C. Danowski I
W.
H. Bolt I
W.
E. Monroe I
B. J. Lefebvre III III III J.
Bell IIR II IIA R. Weber IIR II IIA Sonic Systems International B. J. Astc.1 II II D. Bockey II II J Busbj II II J. Cannizzo II II T. Jones III III R. Curl I
I R.
Busby I
I J. Furr I
I Zetec E. O. McKee IIA Nuclear Energy Cer,.
e, Inc.
CONAM Inspection Division J. T. Lubke II J. Castello I
I b.
Equipment Verification Eddy Current Instrumentation (ET)
Item Serial No.
FM Tape Recorder 0211 Di 2300S 0154 Brush MK 220 Chart Recorder 0037 D: 3300 Plug in 0038 5103-5/D11 Storage for above 0213
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FM 23005 0132 Tape Recorder 0208 Brush MK 220 Chart Recorder 0024 EM 3300 Plug in 0134 5103-N/D11 Storage Scope for above 0007 Oscilloscope B065175 Victor Analyzer 006 Teac Tape Recorder 079 Teac Tape Recorder 3019 Ultrasonic Instruments (UT)
Sonic MK1 780605 Sonic MK1 784522 Sonic MK1 780603 UT Couplant Materials Ultragel Batch No. E 17960 Sonotrace Batch No. 7781 Liquid Penetrant Material, Magnaflux
Cleaner - SKC-S-788015 SKC-NF-78F097 Penetra.t-SKL-HF/SKL-S-5E052 r
Developer SED-S-6D144 Transducers Size Serial No.
Mhz 1"
308859 2.25
.5 x 1" 19265 2.25
.5 x 1" K04812 2.25
.5" L21730 2.25
.375" H24830 5.0
.5" K13841 2.25
.5" K12820 2.25
.375" J05737 5.0
.250" I237?.9 2.25 1"
C29614 1.0 1"
015912 1.0
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.5" H04504 2.25
.375" D24850 5.0
.750" SSI-1 2.25
.5 x 1" 24600 2.25 Eddy Current Standards serial No. I-30-W, /I-32-W Heat Treat No. 8791.
Ultrasonic calioration blocks of CECO, stored on site are used to calibrate instruments for UT examinations.
Radiographic Equipment (RT)
Isotope - S/N-12443 Camera - S/N-0151 (bud)
Densitometer - X-Rite, Model - 301-S/N-269i Survey Meters - 9/N-00485, Model - RP5016C o/N-2454, Model - E130G RT licensee No. 42-16559-01, with Amendment No. 2 Contrary to the above requirements, on April 4, 1975, the NRC inspector observed that the calibration step wedge being used to calibrate the X-Rite Model 301 densitometer, S/N 2699, located in the CONAM portable radiographic facility, was not certificd to a known recognized standard as required by para-graph T-234.2 of ASME Section V.
c.
Eddy Current Exami. cion The inspector observed (W) personnel colletting ET data from the hot and cold leg af the "D" steam generator, - d determined that the examination was being performed in accordance with the approved procedure.
d.
Liquid Penetrant and Radiographic Examination The inspector observed PT and RT examinations being performed by CONAM personnel on the following welds and determined that procedures were being followed, and surveys cenducted.
Valve to spool welds on 2CS 0065, valve S/N-286-903-2-1, weld Nos. 27 and 28.
Valve to spool welds on 2CS 0066, val a S/N"286-903-2-2, weld Nos. 29 and 30.
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Except as noted, no items of noncompliance or deviations were identified.
4.
ISI Data Review and Evaluation The inspector reviewed the following documentation of examinations performed during this inspection period.
a.
UT Examination of Reactor Vessel Closure Head.
Weld No. I through 6, sketch, COM-1-1300.
b.
VT Examinattor of Pressurizer Manway Bolcing, I through 6, sketch, COM-1-2100.
c.
UT Examination of 14" RHR Take Off. Weld Nos. 7 and 8, sketch COM-1-4101.
d.
UT Examination of 8" RHR Hot Leg.
Weld Nos. 11,12,13 and 14, sketch COM-1-4103.
e.
UT Examination of 4" RTD Return Weld Nos. 4 and 5, sketch COM-1-4205.
f.
PT Examination of Loop 3 Reactor Coolant Pipe Weld Nos. 6 and 7.
g.
PT Exacination of 2" and 4" SIS System Weld Nos. 10BW and 11BW, sketch COM-1-4107.
h.
PT Examination of 1 1/2" and 2" Seal Injection System Weld Nos. 9 through 12, sketch COM-1-4113.
1.
PT Examination of 10" Accumulator SIS System Weld No. H6, sketch COM-1-4201.
J.
UT Examination of RC Pump Flywheel, sketch COM-1-5100.
k.
QA Audit Report No. QA-22-79-9 completed on April 3, 1979 of ISI activities.
No items of norcompliance or deviations were identified.
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Exit Interviev At the conclusion of each portion of this inspection the inspector discussed the findings with the licensee's ISI coordinator and at the conclusion of the inspection with licensee representatives (denoted under Persons Contacted)
on April 4, 1979. The inspector summarized the scope and findings of the inspection and discussed the one item of noncompliance identified.
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