ML20140D193

Provides Suppl to 120-day Response Ltr Re GL 96-06 as Promised by 970531

ML20140D193
Person / Time
Site:	Oyster Creek
Issue date:	06/03/1997
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2145, GL-96-06, GL-96-6, NUDOCS 9706100289
Download: ML20140D193 (4)

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GPU Nuclear,Inc.

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U.S. Route #9 South NUCLEAR

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Forked River, NJ 087310388 Tel 609-9714000 June 3,1997 6730-97-2145 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 Generic Letter No. 96-06, dated September 30,1996 Corrective Actions Follow-up to 120-day Response Letter Pursuant to the GPU Nuclear (GPUN) Inc. commitment made in the 120-day responses (Letter Nos. 6730-97-2012 and 2059, dated January 28,1997 and February 26,1997, respectively),

we hereby supplement that response with the information promised by May 31,1997 as follows.

The penetrations identified in our prior submittal as being subject to the postulated conditions causing susceptibility to the phenomena described in GL 96-06 were as listed in the Attachment to the letters referenced above; and, these penetrations are listed below:

1. Shutdown Cooling System Supply (inlet) Line penetration

2. Shutdown Cooling System Return (outlet) Line penetration

3. Reactor Building Closed Cooling Water Return Line penetration

4. Reactor Water Cleanup Supply Line penetration

5. Isolation Condensers A & B Condensate Return Lines (2 - penetrations)

6. Recirculation Loop Sampling Line penetration The corrective actions for Items 1, and 3 above will be to install a check valve designed to relieve pressure inside containment. The corrective action for Item 5 above will be to install a relief valve outside of containment which would discharge downstream of the penetration isolation valves. Two figures are attached which depict the typical design arrangements. New valves installed for these plant modifications will be surveillance checked and tested as I

required pursuant to the plant's IST program,10 CFR 50 Appendix J program or the

.g 9 10 CFR 50.54 Maintenance Program, as applicable.

9706100289 970603 PDR ADOCK 05000219 P

PDR

6730-97-2145 GL 96-06 Response At this time GPUN Inc. believes that Items 2,4, and 6 do not require any corrective actions as previously postulated. Pre!iminary calculations performed using ASME B31.1, the piping code for OCNGS, indicate that these penetrations are not susceptible to overpressure failures in that the calculated stresses are within 120% of the allowable stress at postulated temperatures.

The process for design verification and validation of the new calculations had not been completed. Should the expected results differ from the preliminary evaluations and determination GPUN Inc. will inform the NRC of the corrective actions to be planned.

Corrective actions involving physical modifications to the plant will be documented in the Integrated Schedule for the OCNGS, pursuant to license condition 2.C.(6) of the Full Term Operating License, as previously indicated in our 120-day response. The annual update to the Integrated Schedule will depict these modifications as Category B class project. In the event there are new developments with respect to the use of new or different design criteria, analyses, or methodologies which make modifications unnecessary, GPUN Inc. will advise the NRC of its intent to cancel said project (s) pursuant to the requirements of the Long Range Planning Program implemented by OCNGS, under its full term operating license condition 2.C.(6), noted above.

If you have any questions regarding this document please contact Mr. Gregory M. Gurican, Sr. Licensing Engineer, at 201-316-7972.

Very truly yours,

%Ul%

Michael B. Roche Vice President and Director Oyster Creek Attachments MBR\\gmg cc:

Administrator, Region i NRC Project Manager Sr. Resident inspector Sworn and subscribed to before me this $dday of b

,1997 U

GERALDINE E. LtiVIN f

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Notary Public 2

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