ML17158A156

Discusses 940207 Visit to Util Headquarters in Allentown, PA Re Spent Fuel Pooling Issues

ML17158A156
Person / Time
Site:	Susquehanna
Issue date:	02/28/1994
From:	Rosalyn Jones Office of Nuclear Reactor Regulation
To:	Capra R, Prevatte D AFFILIATION NOT ASSIGNED
Shared Package
ML17158A157	List: ML17158A156 ML17158A163 ML18026A436
References
TAC-M85337, NUDOCS 9403090172
Download: ML17158A156 (6)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 February 28, 1994 Docket Nos.

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

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

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, (SSES)

SPENT FUEL POOL COOLING ISSUE (TAC NO. M85337)

On February 7,

1994, members of the NRC staff visited the headquarters of Pennsylvania Power and Light Company (PP&L) in Allentown, Pennsylvania.

During the visit, the staff reviewed recent licensee calculations regarding the performance of the standby gas treatment system during a boiling spent fuel pool event.

The results of the staff review will be included in the overall safety evaluation being developed as part of the course of action outlined in the November 15, 1993 Task Action Plan.

During the visit, the staff also reviewed modification packages for the standby gas treatment system fire damper fusible links and spent fuel pool remote level and temperature indicators.

The staff obtained a copy of a document showing the-work. status of the fusible link modification.

The staff is forwarding this to you as Enclosure 1.

The staff also obtained a copy of PP&L's safety evaluation for the remote indication of spent fuel pool level and temperature (Enclosure 2),

procurement specifications for the spent fuel pool level element (Enclosure 3),

and vendor catalog excerpts for the spent fuel pool level element (Enclosure 4).

During a January 27, 1994 teleconference between the staff and PP&L, the staff requested additional information regarding the radiological dose estimates provided by PPEL in a submittal dated January 4,

1994.

The staff requested information regarding (1) the significance of leakage from engineered safety features on airborne concentr ations,'2) specific dose estimates'for an operator to verify pool level from the refueling floor, (3) justification of the primary containment leakage rate assumed in the January 4,

1994 dose estimates, and (4) information regarding the proximity of refueling floor drain pipe runs to spent fuel pool cooling operating components.

By letter dated February 2,

1994, PP&L provided information to address questions 1

through 3 above (Enclosure 5).

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Hr. David A. Lochbaum Mr. Donald C. Prevatte February 28, 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.

By this letter, the enclosed documents will be placed in the NRC and local public document rooms.

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

Enclosures:

1.

SGTS Fire Damper Fusible Link Replacement Work Status Sheet 2.

Safety Evaluation:

Remote Indication of Spent -Fuel Pool Level and Temperature 3.

Procurement Request for Spent Fuel Pool Level Indication Equipment 4.

GEMS Catalog Excerpts 5.

Letter from J.'enny, PP&L, to J.

Shea, NRC, dated February 2,

1994 Sincerely,

/s/

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

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Mr. David A:" Lochbaum Mr. Donald C. Prevatte February 28, 1994 The staff is 'reviewing these documents and will continue to pursue additional information as necessary t'o complete the evaluation described in the November 15, 1993 Task Action Plan.

By this letter, the enclosed documents will be placed in the NRC and local.public document rooms.

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

Sincerely,

Enclosures:

1.

SGTS Fire Damper Fusible Link Replacement Work Status Sheet 2.

Safety Evaluation:

Remote Indication of Spen't Fuel Pool Level and Temperature 3.

Procurement Request for Spent Fuel Pool Level Indication Equipment 4.

GEMS Catalog Excerpts 5.

Letter from J.'enny, PP&L, to J.

Shea, NRC, dated February 2,

1994 cc w/o enclosures:

Mr. Robert G.

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

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

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-ENCLOSURE 1

02/07/94 15:44 DESIGN DOCUMENT MANAGEMENT SYSTEM DESIGN MODIFICAT10N -

PAGE 2

MODIFICATION :

DCP 929083 REV:

0 REM MO:

3 DA: 24 YR:

93 MOD TITLE SGTS FIRE DAMPER FUSIBLI LINK REPLACEMENT.CHANGE TO 285F ENG ACCEPT MO:

6 DA: 21 YR:

93 INSTAL HOLD MO:

3 DA: 22 YR:

93 OPERATIONAL MO:

8 DA:

18 YR:

93 PHYS WORK BEGAN MO:

7 DA: 21 YR:

93 HOLD RLSE MO:'

DA: 22 YR:

93 ASSOCIATED MODIFICATIONS:

SPECPARTIAL

• • • PARTIAL TO VIEW THE CDL, HIT ENTER, THEN USE PA1 KEY TO RETURN TO MENU AND CHOOSE SELECTION 10.

CONTINUE TO PAGE 3

FOR ADDITIONAL INFORMATION: Y