IR 05000387/1978019
| ML17138A474 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/06/1978 |
| From: | Ebneter S, Jernigan E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A473 | List: |
| References | |
| 50-387-78-19, NUDOCS 7901180349 | |
| Download: ML17138A474 (10) | |
Text
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U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
8
.8
. ~88-887 78-Docket No.
50-387 License No.
CPPR-101 Priority Category Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Steam Electric Station, Unit
Inspection at:
Berwick, Pennsylvania
.
Inspection conducted:
November 1 and 14-17, 1978
- DA Inspectors:
~i=."
E.
P. Jer'nigan, Re ctor Inspector
/~., 6~
R. A. McBrearty, Rea or Inspector S.
D. Ebneter Section Chief Approved by:
S.
D. Ebneter, Acting Chief, Engineering Support Section No. 1, RC8ES Branch
~- b- ~8 date signed vh ate signed date signed
/z ~ T, dat signed Ins ection Summar Ins ection on November
and 14-17 1978 Re ort No. 50-387 78-19
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of preservice inspection activities and activities associated with storage and installation of the reactor pressure vessel internals.
The inspection involved 44 inspector-hours onsite by two NRC inspectors and a supervisor.
Results:
No items of noncompliance or deviations were identified.
Region I Form 12 (Rev.
Apr il 77)
'7805.9 So>g q
DETAILS 1.
Persons Contacted Penns lvania Power and Li ht Com an L. Ballard, Site gA Engineer R. Beckley, Site gA Engineer E. Carroll, Site gA Engineer
- R. H. Featenby, Project Construction Manager
- J. D. Green, Resident Nuclear gA Engineer
- R. J. Shovlin, Assistant Project Director Bechtel Cor oration
- P. Drucker, Lead gA Engineer
- H. F, Lilligh, Project OA Engineer H.
Oman, Lead Storage and Maintenance Engineer
- B. W. Ott, Lead Welding OC Engineer
- K. G. Stout, Assistant Project Field gC Engineer General Electric Com an F. Forsythe, IPSE Reactor Internals Site Manager D. Hess, Site gA Supervisor
- T. M. Le Vasseur, Site gC Representative W. Miller, Nondestructive Examiner, Level III
- R. M. Pulsifer, Mechanical Engineer R. Wagner, I&SE gA Supervisor
- denotes those present at the exit interview.
2.
Plant Tour The inspectors observed work activities in progress, completed work, and plant status in several areas of the plant during a
general inspection of the plant.
The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements.
Where more detailed inspection.'of an area was con-ducted, the inspection scope and findings are described in other paragraphs of the repor.
Preservice Ins ection PSI Activities a.
Observation of Mork in Pro ress The inspector observed the volumetric examination of the recirculation system nozzle Nl safe end weld using the ultra-sonic technique.
.
The inspector considered the above with respect to criteria delineated in the ASHE Boiler and Pressure Vessel Code,Section XI, 1974 edition through winter 1975 addenda, and
'implementing procedure ISE-gAI-322, revision 3.
The inspector considered the following parameters relative to the performance of the examination'ersonnel certification of each technician performing examinations.
This included the three levels of certi-fication, Level I, II, and III.
Compliance with the implementing procedure with respect to test frequency, scanning techniques (beam angles, scanning surface, scanning rate, and.direction)
and extent of coverage.
Calibration method, including calibration block size and reference reflectors.
Distance amplitude correction technique.
No items of noncompliance were identified.
b.
NDE Procedure Review The inspector reviewed General Electric Company NDE procedures for work activities relative to preseryice examinations.
The following were reviewed with respect to criteria delineated in 10 CFR 50.55a(g)
and the ASHE Boiler and Pressure Vessel Code,Section XI, 1974 edition including the winter 1975 addenda:
ISE-(AI-328, Revision 3, dated November 28, 1977, Met Magnetic Particle Examination Procedure.
ISE-gAI-331, Revision 2, dated June 8, 1978, Color Contrast - Solvent Removable Liquid Penetrant Examination Procedure.
The review of the above procedures considered technical adequacy which included, but was not limited to, the items described below for the magnetic particle and the liquid penetrant method:
(1)
Ma netic Particle Examination (a)
Examination is to be done by the continuous method (current on while particles are being applied).
(b)
'llet particles are suspended in a suitable medium.
(c)
Viewing conditions for fluorescent particles are consistent with the applicable ASME code section.
(d)
Acceptance criteri a are speci fied or referenced
'and are consistent with the applicable ASME code section.
(2)
Li uid Penetrant Examination (a)
The penetrant, penetrant remover, and developer are identified and consistent with the applicable ASME code section.
(b)
Examination surface preparation is specified.
~
(c)
Penetrant materials used for the examination of nickel based alloys and austenitic stainless steel are required to be analyzed for sulfur content and total halogens and the specified limits are consistent with the applicable ASME code section.
(d)
The specified examination surface temperature range is consistent with the penetrant manufacturer's recommendations and is within the range of 60'F to 125 f.
No items of noncompliance'were identifie c.
PSI Data Review The inpector examined records relative to volumetric examin-ation of reactor pressure vessel studs number 1 thru 75 by the ultrasonic technique.
The inspector reviewed the data to ascertain compliance with the ASME B&PV Code,Section XI, 1974 edition including winter 1975 addenda and the implementing NDE procedure.
No items of noncompliance were identified.
4.
Reactor Pressure Vessel RPV Internals a ~
Observation of Work in Pro ress The inspector observed the final torquing of core support bolts No. 4, 5, 6, and 7 in the reactor vessel.
The work was governed by General Electric Company installation in-struction No. 22A4273 and reactor assembly drawing No.
MPL B11-2010.
The work was accomplished using the following equipment:
Williams torque wrench HTW-4RCF, serial No. H40377.
Plard torque multiplier model XYR-22, serial No. 2313.
The above equipment was calibrated using equipment traceable to the National Bureau of Standards as attested to by cali-bration certificate No. 82693, dated October 18, 1978.
The inspector noted that the bolt torque value tolerance used differed from that stated on drawing HPL Bll-2010.
The inspector found that telephone approval for the change was granted by the GE design engineer on October 10, 1978, and that Field Deviation Disposition Request (FDDR) No. KRI-126, Revision 0, was issued on October 31, 1978, and transmitted to GE NED for written approva The inspector observed that the reactor vessel had been established as a "clean area."
All vessel openings were closed except the one used for personnel access to the vessel.
A guard was on duty in the clean room at the access point to assure that only personnel on the access list gained entry, and that the requirement to wear coveralls and shoe covers was observed by those entering the vessel.
The inspector also observed that the work area inside the vessel appeared clean and free of dirt accumulation.
No items of noncompliance were identified.
b.
Review of ualit Records The inspector reviewed Bechtel inspection records associated with storage and maintenance of the following components:
-
. 'ore Support Plate Top Guide Shroud Head and Steam Separator Steam Dryer The review was done to ascertain that inspections were done at the required frequency and that licensee commitments were met.
Records from October 7, 1976, to September 1, 1978, were included.
The inspector also reviewed General Electric Company records related to installation of the following items:
Core Support Plate Jet Pump Nos.
7 and 8 This review was done to ascertain that the installation was do'ne in accordance with applicable procedures and that in-spection hold points were observe The review included traveler cards, joint process control sheets, and special process control sheets.
Installation of the core support plate was not completed at the time of this inspection and this was indicated by the recor ds.
The inspector found that the applicable installation require-ments were met and that required gC inspections were made and properly documented.
No items of noncompliance were identified.
5.
Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on November. 17, 1978.
The inspector summarized the purpose and the scope of the inspection and the finding +4
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