ML17158A121

Responds to Issues Raised in Recipient 921127 Part 21 Rept Re Spent Fuel Cooling.Licensee Safety Evaluation for Replacement of SBGT Sys Fire Damper Fusible Links & Plant EQ List & Study Encl

ML17158A121
Person / Time
Site:	Susquehanna
Issue date:	02/01/1994
From:	James Shea Office of Nuclear Reactor Regulation
To:	Lochbaum D, Prevatte D AFFILIATION NOT ASSIGNED
Shared Package
ML17158A122	List: ML17158A121
References
REF-PT21-94 TAC-M85337, NUDOCS 9402100262
Download: ML17158A121 (4)

Text

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UNITED STATES NUCLEAR REGULATORY COMIVllSSlON WASHINGTON, D.C. 20555-0001 February 1,

1994 Docket Nos.

50-387 and 50-388 Mr. David A. Lochbaum 80 Tuttle Road

Watchung, New Jersey 07060 Mr. Donald C. Prevatte 7924 Woodsbluff Run Fogelsville, Pennsylvania 18051 Gentlemen:

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, (SSES)

SPENT FUEL POOL COOLING ISSUE (TAC NO. M85337)

During the course of the staff's review of the issues raised in your November 27, 1992 Part 21 report, the staff has received additional informa-tion from the licensee on certain specific technical issues.

Following the staff's visit to the site in early December, the licensee provided certain additional documents which we are forwarding to you.

Enclosure 1 contains the licensee's safety evaluation for the replacement of standby gas treatment system fire damper fusible links.

Enclosure 2 is an uncontrolled copy of the SSES "EQ" list, current as of December 3,

1993.

Enclosure 3 is a licensee study entitled "Evaluation of Impact on Equipment Due to Higher Room Temperature Due to Loss of Fuel Pool'ooling with LOCA and LOOP."

Enclosure 4

includes miscellaneous notes supplied by the licensee as followup to a January 7,

1994 teleconference between the licensee, NRC staff and staff from Battelle-Pacific Northwest Laboratory (PNL).

PNL is performing a risk analysis of spent fuel,-pool cooling scenarios as described in Item LC-7 of the November 15, 1993:,Task"Action Plan.

The notes include a set of heat exchanger performance-'.curves for""the spent fuel pool cooling system heat exchangers.

080~<jg 9'402f00262 94020f PDR ADOCK<"05000387

Hr. David A. Lochbaum Hr. Donald C. Prevatte February 1,

1994 The staff is reviewing these documents and will continue to pursue additional information as necessary to complete the evaluation described in the November 15, 1993 Task Action Plan.

If you have any additional comments or questions, please do not hesitate to call me at (301)-504-1428.

Sincerely,

/s/

Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

1.

Safety Evaluation for SGTS Fire Damper Fusible Link Replacement 2.

Susquehanna SES Eg List, dated December 3,

1993 3.

"Evaluation of Impact on Equipment Due to Higher Room Temperatur~'ue to Loss of Fuel Pool Cooling With LOCA and LOOP" dated December 10, 1993 4.

Teleconference Followup Notes cc w/o enclosures:

Hr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Distribution *w/enclosures:

• Docket File JCalvo

• NRC and Local PDR CHiller PDI-2 Reading MO'Brien SVar a

J hea RC1 ark OGC ACRS(10)

EWenzin er, RI

JWhite, RI

• LPrividy, RI OFFICE NAME DATE I 2PH l 94 PDI-2 D

CHi 1 1 er C+

'L I

94 OFFICIAL RECORD COPY DOCUMENT NAME:

L&PDOC.LTR

Hr. David A. Lochbaum Hr. Donald C. Prevatte February 1,

1994 The staff is reviewing these documents and will continue to pursue additional information as necessary to complete the evaluation described in the November 15, 1993 Task Action Plan.

If you have any additional comments or questions, please do not hesitate to call me at (301)-504-1428.

Sincerely,

/s/

Joseph W. Shea, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1.

Safety Evaluation for SGTS Fire Damper Fusible Link Replacement 2.

Susquehanna SES Eg List, dated December 3, 1993 3.

"Evaluation of Impact on Equipment Due to Higher Room Temperature'-

Due to Loss of Fuel Pool Cooling With LOCA and LOOP" dated December 10, 1993 4.

Teleconference Followup Notes cc w/o enclosures:

Mr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Distribution *w/enclosures:

'"Docket File JCalvo

• NRC and Local PDR CMiller PDI-2 Reading MO'Brien SVar a

J hea RCl ark OGC ACRS(10)

EWenzin er, RI

JWhite, RI

• LPrividy, RI OFFICE NAME DATE P I 2/PM 94 i

i 94 PDI-2 D

CHiller C+

I 94 OFFICIAL, RECORD COPY DOCUMENT NAME:

L&PDOC.LTR

Hr. David A. Lochbaum Hr. Donald C. Prevatte February 1,

1994 The staff is reviewing these documents and will continue to pursue additional information as necessary to complete the evaluation described in the November 15, 1993 Task Action Plan.

If you have any additional comments or questions, please do not hesitate to call me at (301)-504-1428.

Since ely, osep W. Shea, Project Hanager roject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1.

Safety Evaluation for SGTS Fire Damper Fusible Link Replacement 2.

Susquehanna SES Eg List, dated December 3, 1993 3.

"Evalu'htion of Impact on Equipment Due to Higher Room Temperature Due to Loss of Fuel Pool Cooling With LOCA and LOOP" dated December 10, 1993 4.

Teleconference Followup Notes cc w/o enclosures:

Hr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101