ML18040A708

Forwards Revised FSAR Section 7.4 Changing Pressure at Which Reactor Shutdown Cooling Sys Will Operate.Rev Will Be Incorporated Into Next FSAR Amend

ML18040A708
Person / Time
Site:	Susquehanna
Issue date:	09/16/1983
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
PLA-1820, NUDOCS 8309200094
Download: ML18040A708 (6)

Text

A, REGULATORY QPORNATION DISTRIBUTION SYN (RIDE)

ACCESSION NBR:8309200094 DOC ~ DATE: 83/09/16 ,NOTARIZED: NO DOCKET

-FACIL:50 388 Susauehanna Steam Electric Stationi Unit 2P Pennaylva 05000388 AUTH. NAME AUTHOR AFFILIATION CURTIS'.H. Pennsylvania Power ff Light Co ~

REC IP ~ f4AME RECIPIENT AFFILIATION SCHWENCERPA ~ Licensing Branch 2

SUBJECT:

Forwards revised FSAR Section 7 ' changing pressure at 'which feactor shutdown cooling sys will operate.Rev will be incorporated-into next FSAR amend.

DISTRIBUT'ION CODE: SOOIS COPIES RECEIVED:LTR TITLE: Licensing Submittal: PSAR/FSAR Amdts 5 L ENCL Related J2 SIZE:

Correspondence NOTES: icv NMSS/FCAF/PM'PDR 2cys- ~ 05000388 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENC ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 NRR LB2 BC 1 NRR LB2 LA 1 PERCH,R. 01 1 INTERNAL: ELD/HDS4 1 IE FILE IE/DEPER/EPB 36 3 'IE/DEPER/IRB 35 1 IE/DEQA/QAB 21 1 NRR/DE/AEAB 1 NRR/DE/CEB 1 NRR/DE/EHEB 1 NRR/DE/EQB 13 2 NRR/DE/GB 28 2 NRR/DE/MEB 18 1 NRR/DE/fYlTEB 17 1 NRR/DE/SAB 24 1 NRR/DE'/SGEB 25 NRR/DHFS/HFEB40 1>> NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 NRR/DL/SSPB 1 NRR/DS I/AEB 26 1 NRR/DS I/AS 9 1 NRR/DSI/CPB 10 1 NRR/DSI/CSB 09 1 NRR/DSI/I CSB 16 1 f4RR/DSI/METB 12 1 NRR/DSI/PSB 19 1 NRR/DSI/RAB 22 1 NRR/DS I/RSB 23 1 04 1 RGN1 3 /MIB 1 EXTERNAL; ACRS 41 BNL(AMDTS ONLY)

DMB/DSS (AMDTS) FEMA REP DI V "'39 LPDR 03 NRC PDR 02 NSIC 05 NTIS NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 57 ENCL

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Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/7705151 Norman W. Curtis Vice President-Engineering & Construction-Nuclear 21 5/770-7501 SEP 16 ts83 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Camnission Washington, D.C. 20555 SUSQUEEtNNA STEAM EL1KTRIC STATION FSAR SECTION 7.4 ER 100508 FILE 841-1 PLA-1820 II Docket No. 50-388

Dear Mr. Schwencer:

In order to support obtaining an'perating license for Susquehanna SES Unit, 2, attached is revised Section 7.4 of the Susquehanna SES FSAR. The revision to this section changes the pressure at which the reactor shutdown cooling system will operate. This change is consistent with the Technical Specifications for both units.

This revision will be incorporated in the next amendment to the FSAR.

Very truly yours,

'42 N. W. Curtis Vice President-Engineering & Construction-Nuclear Attachment cc: R. L. Perch'RC 8309ib 8309200094 05000388 PDR ADQCK PDR

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SS,F.S-FS >P The Beac+or Shu Bown Coolinq System consists of a set of. pumps, valves, heap exchanqe s, and ins rumentation designed "o provide decay heat removal capability "or the core. The system specifically accomplishes the followinq:

The reactor shutdown cooling system is capable of provid'nq cooling for the reac or during shu, down opera+ion after the vessel pressure ': redI>ced .o approximately 98 psiq.

(2) The system is capable of cooling the reactor wa"er to a temperature at which reactor refuel-ng and servicing can be accomplished.

(3) The system is capable of diverting part of the shutdown flow +o a nozzle in the reactor vessel head to condense the steam qenerated from the hot walls of the vessel while it is being flooded.

The system can accomplish its design objectives by a preferred means by directly extracting reactor vessel wa+er from the vessel via the recirulation loop B and routing it to a heat exchanqer and back to the vessel, or by an alternate means by ind iree.ly.

extracting the water via relief valve discharge lines to the suppression pool and routing pool water to +he heat exchanger and back to the vessel.

7. 4. 1. 3. 1. 2 Classif ica+ ion Elec.rical components for the Beactor Shutdown Cooling lode of the Besidual Heat Bemoval Sys em are classified as Safe, y Class  ?

and Seismic Cateqory T.

7. 4. 1. 3. 2 Power Sour ces I

>his system utilizes standby power sources, since the BP3S has safety modes of ope ation (e.q., LpCI) connected to this eguipmen .

7.4.1.3.3 Equipment Design 7.4. 1.3. 3. 1 C'enera 1 The reac"or water is cooled hy tak'g suction from one of he recirculation loops; the wa+er is pumped through the system hea+

7. 4-16

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