ML20035H482

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Discusses Util re-evaluation of Main Stream Tunnel,Per NRC 920601 Suppl Se.Util Determines,Following SBO Event,Temp within Main Steam Tunnel Will Increase to Marginal Level for Prolonged Human Habitability
ML20035H482
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/28/1993
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92178, NUDOCS 9305050135
Download: ML20035H482 (4)


Text

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t O PSEE 1

i Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Depadment

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!y APR 281993 i

NLR-N92178 United States Nuclear Regulatory Commission Document Control Desk i

Washington, DC 20555 Gentlemen:

i STATION BLACKOUT (SBO)

[

HOPE CREEK GENERATING STATION j

DOCKET NO, 50-354 l

On June 1, 1992, Public Service Electric and Gas (PSE&G) f received the, " Supplemental Safety Evaluation, Response to the. Station Blackout Rule."

In this letter, the NRC stated that PSE&G should."... verify that the main steam tunnel is-habitable for the operator to perform the required manual operations during an SBO event."

PSE&G has re-evaluated the habitability.of the main steam tunnel and has determined that following an SBO event, the temperature.within.theLmain steam tunnel _will increase to'a marginal level for prolonged human habitability.

Based on this re-evaluation, PSE&G decided that it'would be more prudent to provide an-I alternate method for providing-isolation of the main steam drain line as discussed in the following attachment.

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I If you have'any questions in regard to this submittal, please contact us.

Sincerely ress:

S.

LaBruna j

_Vice President j

5 Nuclear Engineering Attachments (2)

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'9305050135 930428

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APR 281993 Document Control Desk 2

NLR-N92178 C

Mr. T. T. Martin, Administrator - Region I l'

U.

S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr S.

Dembek, Licensing Project Manager U.

S.

Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr.

T. P. Johnson (S05) r USNRC Senior Resident Inspector Mr.

K. Tosch, Chief NJ Department of Environmental Protec*. ion Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 1

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ATTACHMENT 1 i

NLR-N92178 STATION BLACKOUT (SBO)

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 On December 30, 1991, Public Service Electric and Gas (PSE&G) submitted to the NRC our, " Response to Safety Evaluation on Station Blackout (SBO)."

In this submittal, PSE&G stated that an j

access hatch would be installed in the existing grating above the Main Steam (MS) Drain Valve 1AB-HV-F019 to facilitate manual operation of the valve.

PSE&G has re-evaluated the habitability of the MS tunnel and has determined that it would be more prudent to provide an alternate means for isolating the MS drain line eliminating the need for this access hatch-modification.

The configuration of the MS drain line, including associated branch lines and valving, is shown in Figure 1 (Attachment 2).

Administrative and procedurel controls will be implemented to maintain valves 1AB-HV-F020, 1AB-HV-F021 and either V018 or V019 in a closed position during plant operations above 15% power.

These valves and the associated system piping are ASME Section III components and are classified as Q, which is defined as seismically supported and designed to Saintain its integrity during a design basis event.

However, these valves are not contained in Hope Creek's ASME Section XI inservice testing program for valves.

Based on the proposed administrative and procedure controls discussed above and valve IAB-HV-F033 being less than 3",

the MS drain line is being excluded based on exclusion criteria numbers 1 and 5 of Regulatory Guide 1.155, Section 3.2.7 and NUMARC 87-00,Section 7.2.5.

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