IR 05000387/1985010
| ML17156A252 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/13/1985 |
| From: | Durr J, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17156A251 | List: |
| References | |
| 50-387-85-10, NUDOCS 8505200449 | |
| Download: ML17156A252 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-387/85-10 Docket No.
50-387 License No.
NPF-14 Priority Category C
Licensee:
Penns lvania Power 5 Li ht Com an Facility Name:
Sus uehanna Steam Electric Station Unit
Inspection At:
Salem Townshi Penns lvania Inspection Conducted:
March
22 1985 Inspectors 6 - ~
R. A.
McB r y, Reactor En eer Approved by: ~.
.
t Io~
J..
Durr, Chief E gi eering Branch, DRS date date Ins ection Summar
- Ins ection on March ll 22 1985 Re ort No. 50-387/85-10
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11 program review, review of videotapes of in-vessel inspections, review of data, NDE Procedures, MINAC radiography activities, review of QA/QC involvement with ISI activities and observations of work in progress.
The inspection involved 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> onsite and 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in office by one regional based inspector.
Results:
No violations were identified.
8505200449 8505i4 PDR ADOCK 05000387
PDR Details 1.
Persons Contacted Penns lvania Power
& Li ht Com an PPEL
'R. A. Beckley, General Supervisor QC J.
Bognet, Project Manager MINAC
"R. A. Breslin, Supervisor Nuclear Maintenance Support
"R.
G.
Byram, Technical Supervisor
- E. Carroll, Nuclear Support ISI Supervisor C. Hersh, Analyst T. Hiller, IEG Engineer
'T.
K. Steingass, NDE Level III
"D. Thompson, Assistant Plant Supervisor General Electric Com an G.E.
D. L. Richardson, NDE Level III Southwest Research Institute SWRI E. Reusher, NOE Level III R. Shimkus, NDE Level III CTS Power Services Inc.
K. Clayton, QA Supervisor U.S. Nuclear Re viator Commission
- R. H. Jacobs, Senior Resident Inspector
- L. Plisco, Resident Inspector
- Denotes those present at the exit meeting.
2.
Inservice Ins ection ISI Pro ram The current outage at Susquehanna, Unit 1 is the first refueling outage in the first period of the first ten year inspection interval.
The nondestructive examinations are governed by the ASME Boiler and Pressure Vessel Code, Section
ÃI, 1980 Edition through winter 1980 addenda, and are performed by Southwest Research Institute personnel, the licensee's ISI vendor.
The inspector reviewed the licensee's ISI program to ascertain that regulatory requirements were met, and that related ISI activities are adequately controlled by the licensee.
The following were included in the inspector's review:
~
NSI-QA-10. 11, Revision A, "ISI Data Management System (STARS)"
s
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NDI-QA-5.3.4, Revision 1,
"ASME Section XI Repairs, Replacements and Modifications"
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OPS-9,
"Control of Modification and Design Activities"
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AD-QA-502, Revision 5,
"Work Authorization System" The inspector found that the aforementioned documents provide adequate control of ISI activities at the facility.
NSI-QA-10. 11, Rev.
A appears to be a
particularly effective computerized system for tracking the various aspects of the program, and for determining examination status during the interval.
The ISI program is included in the licensee's controlled document system, and procedures are provided to assure that modifications, design changes and repairs are incorporated in the ISI program.
The ISI staff is adequate for the work load and is comprised of technically competent individuals.
No violations were identified.
3.
Reactor Pressure Vessel Internals Remote, underwater visual examinations in the reactor vessel were in progress during the course of this inspection.
The inspections were being performed by CTS Power Services, Inc.,
the licensee's contractor, and were recorded on video tape.
The inspector reviewed the inspection tapes associated with the following components:
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"A" sparger
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Core spray "C" 5 "D" sparger
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Jet pump ¹6 hold down yoke
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Steam dryer support ring
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Steam dryer support bracket - 184 azimuth The review was done to ascertain the adequacy of the tape to assess the component integrity.
The tapes were found to be of excellent quality and showed clear, well defined views of the areas of interest.
The initial inspections revealed questionable conditions associated with each item.
Additional inspections which incorporated various angles of view, lighting arrangements and close up views, confirmed cracks in the steam dryer support bracket, the steam dryer support ring and the
"D" core spray sparger.
The remaining items listed above were found to be free of relevant indications.
Dry tube examinations are planned and examination of the top guide was in progress, however no results were available at the time the inspector left the sit The most severely cracked item appeared to be the steam dryer support bracket, which is welded to the reactor vessel wall.
Ultrasonic examinations were made of the support bracket from the outside surface of the vessel and from the three available surfaces of the bracket inside the vessel.
The examinations were performed using 0'nd
transducers by two General Electric Company NDE Level III individuals, and by the licensee's Level III.
In addition to the ultrasonic examination, liquid penetrant examination was done of the available surfaces.
These examinations were done to assess the extent of the visible cracks, and to determine whether the cracks extended into the vessel base metal.
The results of the examinations indicated that crack propagation was away from the vessel wall and no indications of cracks were found to extend into the vessel base metal.
Metallurgical samples were removed from the cracked areas, and have been sent for analysis to a
General Electric laboratory.
The licensee and General Electric are investigating methods for removal and replacement of the cracked support.
No information regarding the repair was available at the time of the inspector's exit meeting.
No violations were identified.
ualit Assurance/ ualit Control A/
C The inspector interviewed QA/QC personnel and reviewed licensee audit report 8P-84-14 to ascertain that ISI activities and the ISI vendor are included in the QA/QC program.
Audit P-84-18 was 'done by the licensee on May 14-18, 1984, at Southwest Research Institute, San Antonio, Texas, and examined the SWRI nondestructive examination certification program and implementation of the program.
Audit findings were adequately documented SWRI responses to audit findings were included in the documentation, and findings were pro'perly closed out.
The inspector, additionally, determined that the licensee's Level III performs surveillances of SWRI activities at the site, including ultrasonic examinations and radiography, using MINAC, of recirculation system riser welds which cannot be examined with ultrasonic techniques.
No violations were identified.
Procedure Review The inspector reviewed nondestructive examination procedures to ascertain compliance with ASME code and regulatory requirements, and with licensee commitments.
The following were included in the inspector's review:
I E
j
~
~
TP-ISI-307, Revision
(SWRI-NDT-600-31, Revision 12),
"Manual Ultrasonic Examination of Austenitic Pressure Piping Welds"
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TP-ISI-308, Revision 1,
"Manual Ultrasonic Examination of Ferritic Pressure Piping Welds" Section 5.3 of TP-ISI-307 permits the use of flat calibration blocks when the contact surface of the part to be examined is greater than 20 inches in diameter.
The ASME Code,Section XI, Appendix III, 1980 Edition through winter 1980 addenda requires that the calibration block shall be made from material of the same nominal diameter and nominal wall thickness or pipe schedule as the pipe to be examined.
The inspector examined the calibration block used for welds which are examined in accordance with the procedure, and found that it met the code requirement regarding diameter and nominal thickness.
The inspector found no calibration blocks for piping examinations at the'ite which were flat.
The inspector suggested to the licensee that the procedure be revised to bring it into compliance with Section XI.
This is considered unresolved pending licensee action and subsequent NRC review (387/85-10-01).
No violations were identified.
6.
MINAC Radio ra h
of Recirculation S
stem Welds The licensee has elected to radiographically examine the following recirculation system welds using the MINAC system developed by the EPRI NDE Center:
~Lpp VRR-B31-1-FW-A14, IHSI heat ¹021 VRR-B31-FW-A13, IHSI heat ¹022 VRR-B31-1-FW-A12, IHSI heat ¹025 VRR-B31-1-FW-A11, IHSI heat ¹027 VRR-B31-1-FW-A10, IHSI heat ¹028 VRR-B31-1FW-A19, IHSI heat ¹137 VRR-B31-1-FW-A18, IHSI heat ¹138 VRR-B31-1-FW-A17, IHSI heat ¹139 VRR-B31-1-FW-A16, IHSI heat ¹140 VRR-B31-1-FW-A15, IHSI heat ¹141
II
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~~~~~
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YRR-B31-2-FW-B14, IHSI heat ¹069
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VRR-B31-2-FW-B13, IHSI heat ¹070
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VRR-B31-2-FW-B12, IHSI heat ¹073
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VRR-B31-2-FW-B11, IHSI heat ¹074
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VRR-B31-2-FW-B10, IHSI heat ¹076
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VRR-B31-2-FW-B19, IHSI heat ¹142
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YRR-B31-2-FW-B18, IHSI heat ¹143
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YRR-B31-2-FW-B17, IHSI heat ¹144
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VRR-B31-2-FW-B16, IHSI heat ¹145
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VRR-B31-2-FW-B15, IHSI heat ¹146 The MINAC radiography was being done by SWRI per sonnel, and the film interpretation was done by the licensee Level III and a
consultant contracted by the licensee.
Films representing the following welds were reviewed by the inspector:
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VRR-B31-1-1-FW-A11, Sweepolet to riser weld
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VRR-B31-2-FW-B10, Sweepolt to riser weld
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VRR-B31-2-FW-B13, Sweepolt to riser weld The licensee Level III informed the inspector that approximately
percent of the welds which were completed met the density requirements, which is listed as an essential variable of the technical basis established by the NRC, the EPRI NDE center and the BWR owner's group for using MINAC at the facility.
He stated that, in those cases where the technical basis density requirement could not be met, that the ASME code requirements were met.
The ASME code permits densities ranging from 1.8 to 4.0 and the technical basis restricts film density to the range from 2.8 to 3.5.
As part of the inspector's film review, densitometer readings were taken at selected areas of each film to confirm the density documented by the film interpreter.
The inspector's review indicated the following:
Weld FW-B10, station marker "3" missing in view 3-4, maximum density of 4.38 in view 6-0 (exceeds technical basis and code maximum).
Weld FW-B13, penetrometer in area of interes gt
,A
The inspector stated that the deviations from acceptable film densities and the apparent incomplete coverage of areas of interest was considered unresolved pending licensee action to verify that acceptable films are available (387/85-10-02).
No violations were identified.
7.
Observations of NDE in Pro ress The inspector observed the ultrasonic examination of weld VRR-B31-2-FW-B7, IHSI heat ¹062.
The weld was examined by SWRI personnel using the technique whereby the Level II individual observes an ultrasonic instrument which is located in a relatively radiation free area of the plant remote from the weld.
He is in constant voice contact with the Level I probe manipulator and a closed circuit television system permits the manipulator to observe the ultrasonic display whenever it becomes necessary for him to do so.
The inspector's observations were made to ascertain compliance with applicable requirements and licensee commitments.
No violations were identified.
8.
Data Review and Evaluation The inspector selected for review NDE data representing examinations which were performed during the current refueling outage.
The review was done to ascertain that recorded indications were properly evaluated, and that programmatic requirements were met.
Data representing the following welds were included in the inspector's review:
Li uid Penetrant Examination
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Standby Liquid Control System weld SP-DCA-106-1FW-8, pipe to fluid head.
Ultrasonic Examination The following recirculation system welds were examined subsequent to IHSI treatment:
VRR-B31-2-10-A, 28" diameter tee to pipe.
VRR-B31-2-10-C, 28" diameter pipe to tee.
VRR-B31-2-9-2-A, 22" diameter pipe to end cap.
VRR-B31-2-9-2-D, 22" diameter tee to pipe
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VRR-B31-2-FW-B5, 28" diameter elbow to pum.
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VRR-B31-2-3-D, 38" diameter pipe to elbow.
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VRR-B31-2-9-1-J, 22" diameter pipe to end cap.
Ultrasonic indications which were detected in the welds were evaluated by a
SWRI Level III individual.
The evaluation process consisted of plotting the location of the indication, comparing the data to preservice inspection results and construction radiographs, and the use of supplemental ultrasonic examinations including the use of the SLIC-40 transducer.
No violations were identified.
Personnel uglification/Certification Records The inspector reviewed the records of individuals who performed remote, in-vessel visual examinations, radiographic examinations and ultrasonic examinations at the site.
One SWRI ultrasonic Level II technician was not listed in the EPRI NDE Center register of IGSCC qualified personnel, but a telephone inquiry to the NDE Center confirmed that he was properly qualified and would be included in the next edition of the register.
The inspector found that the records of four of the SWRI Ultrasonic Level II individuals were incomplete in that the documented hours of training for each of the individuals was less than the
hours required by SNT-TC-lA.
Each individual must receive
hours of training to become Level I,
and
additional hours to become Level II.
The records indicated that three of the individuals each received a total of 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> training, and the fourth received a
total of
hours of training.
Additionally, the records indicated that two of the individu'als had less than the
months experience required by the SNT-TC-1A (3 months for Level I
and 9 additional months for Level II).
Additional, information was requested by the licensee from SWRI, but was not yet received when the inspector left the site.
This is considered unresolved pending receipt and licensee review of the information and subsequent review by the NRC (387/85-10-03).,
No violations were identified.
Unresolved Items Unresolved items are items about which more information ascertain whether they are, acceptable,'iolations Unresolved items ape discussed in paragraphs 5,
6 and 9.
Exit Interview is required to or deviations.
The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on March 22, 1985.
The inspector
-i
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+ p.
V summarized the purpose and scope of the inspection and the findings.
At no time during this inspection was written material provided by the inspector to the licensee.