ML18030A238

Forwards Revised Responses to Questions 32.7 & 32.24 of FSAR

ML18030A238
Person / Time
Site:	Susquehanna
Issue date:	03/25/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
PLA-689, NUDOCS 8103310566
Download: ML18030A238 (4)

Text

REGULATORY VFORRATIOQ DISTRIBUTION SY'Rli (RIDS)

ACCESSION N8R:810331056o DUC DATE: 81/03/25 t"OTARIZED: NO DOCKET FAG IL'usauehanna 50-388 S

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team El ectri c Steam Electric Stat i one Uni t 1 Pennsy1 va p

Stationr Unit 2P Pennsylva 05000387 05000388 usquehanna AUTH ~ . AUTHOR AFFILIATION CURTrS V..<. Pennsylvania Power 4 Light Co ~

REC IP ~ VAElIE REC IP I EN T AF F IL I ATIOIV YOUNGBLOOOrB,J, Operating Reactors Branch 1

SUBJECT:

Forwards revisea responses to Questions 032.7 R 032,24 of FSAR ~

OISTRISUTIOR COOE: 800IS COPIES RECEIVES:LTR J ERCL J SIZE:

TITLE: PSAR/FSAR AMDTS and Related Corresponaence NOTES:Send IS,E 3 conies FSAR 4 all amends. 05000387 Send I8E 3 copies FSAR A all amends. 05000388 REC IP IEIVT COPIES RECIPIENT COPIES ID CODE/NAH LTTR ENCL ID CODE/NAME LTTR ENCL ACTI, ON: A/O LICENSNG 1 0 YOUNGBLOOOEB 1 0 RUSHBROOKP 4 1 0 STARKERS Ott 1 1 ACCID EVAL BR26 'NTERNAL:

1 1 AUX SYS BR 07 1 1 CHEM ENG BR Oo 1 1 CONT SYS BR 09 1 1 CORE PERF BR 10 1 1 EFF TR SYS BR12 1 1 E41ERG PREP 22 1 0 EQUIP QUAL BR 13 3 GEOSC IENCES 14 1 1 HUM FACT ENG BR 1 1 HYD/GEO BR 15 2 2 ISC SYS BR 16 1 1 IR,E Ob 3 3 LIC GUID BR 1 1 LIC QUAL BR 1 1 t 1ATL EIVG BR 17 1 SECH ENG BR 18 1 1 t1P A 1 0 NRC POR 02 1 1 OELO 1 F OP LIC BR 1 1 POrtER SYS BR 19 1 1 PROC/TST REV 20 1 1 QA BR 21 1 1 S BR2? 1 1 REAC SYS BR 23 1 1 G F IL 01 1 . 1 SIT AhAL BR 1 ENG BR25 ItvTERAC BR 2'YS 1 1 1 1 EXTERNAL: AC"S 27 ib 16 LPDR 03 1 1 NSIC 05 1 TOTAL NUMBER OF COPIES REQUIRED LTTR 57 ENCL 51

TWO NORTH NINTH STREET, ALLENTOWN, PA. I 8 I 0 I PHONEr (215) 770-5151 NORMAN W. CURTIS vice Piesidenr-Engineering rL construe!ion-Nucrear 7705381 March 25, 1981 Mr. B.J. Youngblood, Licensing Branch 1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Susquehanna Steam Electric Station Docket Nos. 50-387 and 50-388 Revised Responses to guestions 032.7 and 032.24 ER100450 Fil e 841-2 PLA-689

Dear Mr. Youngblood:

Attached are the revised responses to questions 032.7 and 032.24.

Very truly yours, N. W. Curti s Vice president-Engineering and construction-Nuclear CC: R.M. Stark

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bcc: N.W. Curtis W.E. Barberich B.A. Snapp C.T. Coddington R.J. Shovlin goo/

(/~t PENNSYLVANIA POWER IL LIGHT COMPANY

SSES-FSAR UESTZON 032.7 Section 7.1.2a.1.4.6.3 of the FSAR states that as a power generation design bases for the Rod Block Monitor, it will prevent local fuel error. Provide damage that may result from a single rod withdrawal the justification for classifying this as a power generation design bases and not a safety design bases.

RESPONSE

A GE/NRC generic meeting was held on January 26, 1981 to discuss the Reactor Manual Control System and to specifically address the appropriateness of utilizing the RBM in transient, mitigation.

The new electronic RMCS being utilized at SSES was described in detail with an emphasis upon reliability, redundancy and self-testing features.

The NRC, in the January 26 meeting, indicated approval of the design and use of RBM system in transient analysis.

Rev. 22, 4/81 032.7-1

SSES-FSAR UESTION 032.24:

The accident analysis presented in Chapter 15 is based, in part, on the assumption that the Rod Block Monitor (RBM) acts to mitigate the consequences of a continuous control rod withdrawal. The staff's position is that the RBM is a protection system and must be designed, fabricated, installed, tested and subjected to all of the design criteria which are applicable to a reactor trip system. Revise the FSAR to reflect the importance of the RBM in accordance with the requirements of Section 7.2 of the "Standard Format", Regulatory Guide 1.70. Identify and justify any exceptions.

RESPONSE

A GE/NRC generic meeting was held of January 26, 1981 to discuss the Reactor Manual Control System and to specifically address the appropri-ateness of utilizing the RBM in 'transient mitigation.

The new electronic RMCS being utilized at SSES was described in detail with an emphasis upon reliability, redundancy and self-testing features.

The NRC, in the January 26 meeting, indicated approval of the design and use of RBM system in transient analysis.

Rev. 22, 4/81 032.24'=1