ML18030A238
| 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 FAGIL'usauehanna S team El ectri c Stat i one Uni t 1 p Pennsy1 va 50-388 usquehanna Steam Electric Stationr Unit 2P Pennsylva AUTH ~
AUTHOR AFFILIATION CURTrS V..<.
Pennsylvania Power 4 Light Co ~
REC I P ~ VAElIE REC IP I EN T AF F ILI 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.
Send I8E 3 copies FSAR A all amends.
DOCKET 05000387 05000388 05000387 05000388 REC IP IEIVT ID CODE/NAH ACTI,ON:
A/O LICENSNG RUSHBROOKP 4
'NTERNAL:
ACCID EVAL BR26 CHEM ENG BR Oo CORE PERF BR 10 E41ERG PREP 22 GEOSC IENCES 14 HYD/GEO BR 15 IR,E Ob LIC QUAL BR SECH ENG BR 18 NRC POR 02 OP LIC BR PROC/TST REV 20 S
BR2?
G F IL 01 ENG BR25 COPIES LTTR ENCL 1
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1 1
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1 RECIPIENT ID CODE/NAME YOUNGBLOOOEB STARKERS Ott AUX SYS BR 07 CONT SYS BR 09 EFF TR SYS BR12 EQUIP QUAL BR 13 HUM FACT ENG BR ISC SYS BR 16 LIC GUID BR t 1ATL EIVG BR 17 t1P A OELO POrtER SYS BR 19 QA BR 21 REAC SYS BR 23 SIT AhAL BR 2'YS ItvTERAC BR COPIES LTTR ENCL 1
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EXTERNAL: AC"S NSIC 27 05 ib 16 1
LPDR 03 1
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 Mr. B.J.
Youngblood, Licensing Branch 1
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 March 25, 1981 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
+
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CC:
R.M. Stark bcc:
W.E.
B.A.
C.T.
R.J.
N.W. Curtis Barberich Snapp Coddington 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 damage that may result from a single rod withdrawal error.
Provide 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