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Insp Rept 50-219/87-38 on 871102-06.No Violations Noted. Major Areas Inspected:Licensee Response to Generic Ltr 84-11 & Status of Activities Re Drywell Wall Thinning
	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: ML20239A700; ML20239A705;
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)
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U.S. NUCLEAR REGULATORY COMMISSION '

REGION I

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Report No. 50-219/87-38 :

Docket No. 50-219

License No. DPR-16 Priority: -

Category: C

Licensee: GPU Nuclear Corporation

P. O. Box 388 a

Forked River, NJ 08731

Facility Name: Oyster Creek Nuclear Generating Station j

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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

G. Rhedrick, Lead ISI Engineer

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- ,

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 i

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

GL 84-11. 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

Shutdown Cooling

Reactor Water Cleanup

- Core Spray

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"

l 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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ML20239A705

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