ML20239A705
| ML20239A705 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/14/1987 |
| From: | Mcbrearty R, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20239A701 | List: |
| References | |
| 50-219-87-38, GL-84-11, IEB-82-03, IEB-82-3, IEB-83-02, IEB-83-2, NUDOCS 8712300012 | |
| Download: ML20239A705 (4) | |
See also: IR 05000219/1987038
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION I
1
Report No.
50-219/87-38
Docket No.
50-219
License No.
Priority:
-
Category:
C
Licensee: GPU Nuclear Corporation
P. O. Box 388
a
Forked River, NJ 08731
Facility Name: Oyster Creek Nuclear Generating Station
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Inspection At:
Forked River, New Jersey
Inspection Conducted:
November 2-6, 1987
Inspectors:
NIW-
II/'4 f 6 7
f R. A. McBrearty, R'eactor Engineer
date
Approved b :
e
9-
t s//1/E7
J. RT Strosniderf Chief, Materials and
date
Processes Section, EB, DRS
Inspection Summary:
Inspection on November 2-6, 1987 (Inspection Report
No. 50-219/87-38).
Areas Inspected: A routine, announced inspection was conducted by one
regional based inspector of the licensee's response to Generic Letter 84-11,
and the status of activities associated with the drywell wall thinning.
Results: No violations were identified.
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DETAILS
1.
Persons Contacted
GPU Nuclear Corporation (GPUN)
- E. Ahern, ISI Engineer
- J. Christian, Le d QA Auditor
D. Covill, Mater fals Engineer
- R. Fenti, Operc tions QA Manager
- M. Heller, Licensing Engineer
R. Lorenzo, Manager - Oyster Creek Projects
R. Ostrowski, ISI Program Manager
R.' Turner, NDE Supervisor - Level III
- Denotes those present at the exit meeting.
2.
Licensee Actions Taken to Implement Generic Letter (GL) 84-11
Inspections which were conducted pursuant to IE Bulletins 82-03,
Revision 1, and 83-02, and the NRC August 26, 1983 Orders revealed inter-
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granular stress corrosion cracking (IGSCC) in large diameter recirculation
and residual heat removal piping at several operating boiling water
reactors. As a result of these inspections, Generic Letter 84-11 was
issued on April 19, 1984 to require an ongoing program for similar re-
inspections at all operating BWRs.
Bulletin 82-03, Revision 1, was issued
on October 28, 1982, and included all licensee's whose plants were cur-
rently in or scheduled to be in a refueling mode or extended outage
through January 31, 1983.
Oyster Creek was included in that group and was
required to demonstrate, on representative service-induced cracked pipe
samples, the effectiveness of the detection capability of the ultrasonic
methodology planned to be used to examine welds in recirculation system
piping.
The Electric Power Research Institute (EPRI) arranged to have
cracked samples from the Nine Mile Point Unit 1 facility available at
Battelle Memorial Institute at Columbus, Ohio, for industry demonstrations
of UT methodology.
Two GPU representatives performed the demonstration on
October 29, 1982, at Battelle and because IEB 82-03, Revision 1, required
that representative UT personnel from the licensee's ISI contractor per-
form the demonstration, on December 14,.1982, the licensee sent Magnaflux
Corporation UT personnel to Battelle.
The demonstrations were witnessed,
and the results were evaluated by an NRC Region I representative and,
based on acceptance criteria which were developed by the NRC staff, the
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licensee was informed that the results of both demonstrations were
acceptable.
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Generic Letter 84-11 requires that a reinspection program of piping
susceptible to IGSCC commence within about two calendar years, adjusted
to coincide with the next scheduled outage, from the previous inspection
performed under IE Bulletins 82-03, 83-02, or the NRC August 26, 1983
Order.
It further requires that the reinspection include certain stain-
less steel welds, susceptible to IGSCC, in piping equal to or greater than
4" in diameter, in systems operating over 200 F, that are part of or
connected to the reactor coolant pressure boundary, out to the second
isolation valve.
The inspector reviewed licensee documentation regarding the examinations
which were performed with respect to IE Bulletin 82-03, Revision 1, and
The 82-03 examinations were done during the 1983 refueling
outage. Additional IGSCC examinations were performed in 1984 as a result
of the detection of leakage at a weld in the Isolation Condenser System
due to a through wall crack in the weld.
The licensee's response to GL 84-11, dated October 9, 1984, provided its
inspection program for the 1986 Cycle 11 refueling outage to the NRC.
The response discussed the scope of inspections, examination criteria,
repair methods, mitigating actions, leak detection and leakage limits.
Examinations planned by the licensee for the Cycle 11 outage included
welds in the following systems:
Recirculation
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Isolation Condenser
In addition to the ultrasonic examinations which were performed in 1986,
the licensee applied Induction Heating Stress Improvement (IHSI) to 64
recirculation system welds. All of the treated welds were ultrasonicly
examined subsequent to the IHSI treatment.
The inspector found that GL 84-11 requirements were met by the licensee,
and this finding was supported by the Safety Evaluation by the Office of
Nuclear Reactor Regulation dated November 14, 1986.
No violations were identified.
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3.
Drywell Wall Activities Status
The status of the drywell wall inspection activities was as follows:
Ultrasonic thickness measurements at the 50'2" elevation were
completed along a 1" wide, 360 strip around the inside surface of
the wall.
Preliminary measurements were made at the 87'5" elevation along a 1"
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wide, 11' long strip.
Additional measurements at the 87'5" elevation were planned along a
continuation of the 1" wide strip completely around the wall.
Two core samples were removed from selected locations at the 50'2"
elevation.
The licensee was considering the removal of a core sample at the
87'5" elevation.
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The two removed core samples were sent to the GPU laboratory at Reading,
Pennsylvania, for analysis where the work was still in progress at the
time of th4s inspection.
Subsequent to this inspection, on November 13,
1987 the licensee met with NRC representatives from NRR and Region I and
presented the results of the drywell insp-
lon representatives from NRR
and Region I and presented the results of
ie drywell inspection
activities and drywell structural and corrosion evaluations. Material
physical properties obtained from certified mill test reports were used
in the licensee's evaluation of fitness of the drywell wall for continued
serv $ce. The inspector reviewed the certified test reports and the
licensee's calculations and verified that the material property values
used by the licensee for his calculations were correct and were traceable
to the specific material in the drywell wall.
4.
Exit Meeting
The inspector met with licensee representatives denoted in Paragraph 1 at
the conclusion of the inspection on November 6, 1987.
The inspector
summarized the purpose and scope of the inspection, and the findings.
At
no time duting this inspection was written material provided by the
inspector to the licensee.
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