ML18030A296
| ML18030A296 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/01/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18030A297 | List: |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8106050311 | |
| Download: ML18030A296 (5) | |
Text
REGULATORY FORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR:8106050311 OOC ~ DATE-'8l/06/Ol NOTARIZED:
NO FACIL:50-387 Susauehanna Steam Electric Station~
Uni t 1 i Pennsyl va 50 388 Susquehanna Steam Electric Station~
Unit 2i Pennsylva AUTH BYNAME AUTHOR AFFILIATION CURTISF N ~ 'Pl ~
Pennsylvania Power
& light Co, RECIP.VA~E RECIPIENT AFFILIATION YOUNGBLOOOiS,J ~
Licensing Br anch 1
SUBJECT:
For wards response to IE Bul 1etin 80 06'Engineer ed Safety Feature (ESF)
Reset Controlsi" as requested in SER Outstandina Issue 44, DISTRIBUTION CODE:
8001S COPIES RECEIVED: LTR JENCL J.
SIZE:
TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES:Send I&E 3 copies
'FSAR
& all amends.1 cy.'BNR LRG PM(LE RIB)
Send I&E 3 copies FSAR
& all amends.
DOCKET ¹ 543k0 000 8
05000387 05000388 RECIPIENT ID CODE/NAME ACTION; A/0 LICENSNG LIC BR ¹2 LA INTERNAI.:
ACC ID EVAL BR26 CHEMI KVG BR 11 CORK PKRF BR 10 K<ERG PREP 22 E<RG PR> LIC 36 FK'IA RKP OI V 39 HUM FACT KNG 40 I&C SYS SR 16 LIC GUIO BR 33 LIATL ENG BR 17 MPA OELO PONER SYS BR 19 QA BR 21 RKAC SYS BR 23 SI T ANAL BR 24 COPIES LTTR ENCL 0
1 0
1 1
1 1
1 1
1 0
3 3
1 1
1 1
1 1
1 1
1 1
1 0
1 0
1 1
1 1
1 1
1 1
RECIPIENT IO CODE/NAME LIC BR ¹2 BC STARKgR ~
04 AUX SYS SR 27 CONT SYS BR 09 EFF TR SYS BR12 EMRG PRP DEV 35 EQUIP QUAL BR13 GEOSC IKNCES 28 HYO/GEO BR 30 I&K 06 L IC QUAL BR 32 MECH FNG BR 18 NRC PDR 02 OP L IC BR 34 PROC/TST REV 20 BR22 REG F
01 CT ENG BR25 COPIES LTTR ENCL 1
0 1
1 1
1 1
1 1
1 1
1 3
3 2
2 2
2 3
3 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
=XTERNAL: ACRS NSIC 41 05 16 16 1
1 LPDR 03 J+g (8
TOTAL NURSER OF COPIES REQUIRED:
LTTR +
ENCL
+5
TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEr t215) 770-5151 NORMAN W. CURTIS Vice President-Engineering IL Construction-Nuclear 770 5381 June 1,
1981
'~// (
J
~
Mr. B. J. Youngblood, Chief Licensing Branch No.
1 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket Nos.
50-387 50-388 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE 8'44 ER 100450 FILE 841-2 PLA-821
Dear Mr. Youngblood:
Attached is a copy of Pennsylvania Power and Light Company's response to IE Bulletin 80-06 as requested in SER Outstanding Issue 8'44.
Very truly
- ours, N.
W. Curtis Vice President-Engineering and Construction-Nuclear CTC/mks Attachment got(
S (I(
8 1060 ~0 ~i PENNSYLVANIA POWER 8
LIGHT COMPANY
AFFIDAVIT COUNTY OF LEHIGH COMMONWEALTH OF PENNSYLVANIA)
)
I, NORMAN W. CURTIS, being duly sworn according to law, state that I am Vice President, Engineering 6 Construction-Nuclear of Pennsylvania Power 6
Light Company and that the facts set forth on the attached response by Applicants to IE Bulletin 80-06 are true and correct to the best of my knowledge, information and belief.
Norman W. Curtis Vice President, Engineering 6 Construction-Nuclear Sworn to and subscribed before me this $ 7~~ day of May, 1981.
Notary P lic
'30HN P. t<'ALLER, jR., Hot P
ic Allen!own, Lehigh County, a.
M Cornrnission Expires y
h5a 29,1980 y
Mr. Boyce H. Grier Page 2
MAY 27 1881 GROUP II Unit.i Unit 2 HV-16108 A1&A2 HV-16116 Al&A2 HV-18781
. Al&A2&Bl&B2 HV-18782 A1&A2&B1&B2 HV-18791 A1&A2&B1&B2 HV-18792 A1&A2&B1&B2 HV-B31-1F019 HV-B31-1F020 HV-C51-1J004 A-E HV-Ell-1F079 A&B HV-Ell-1F080 A&B HV-26108 A1&A2 HV-26116 Al&A2 HV-28781 A1&A2&B1&B2 HV-28782 A1&A2&B1&B2 HV-28791 A1&A2&B1&B2 HV-28792 Al&A2&Bl&B2 HV-B31-2F019 HV-B31-2F020 HV-C51-2J004 A-E HV-E11-2F079 A&B HV-E11-2F080 A&B 2.
The test described in item 2 of the bulletin will be performed during the preoperational test phase prior to fuel load.
3.
Valves listed in Group I above will not be modified.
Justification has been provided to NRC in PLA-659 dated March 16,
- 1981, and PLA-715 dated April 14, 1981, which provided responses to NUREG 0737 item II.E.4.2.
The logic for valves listed in Group 2 will be modified so that the valves remain in their emergency mode upon the reset of an ESF actuation signal.
These modifications are scheduled to be completed prior to fuel load.
Very truly yours, N. W. Curtis Vice President-Engineering
& Construction-Nuclear Affidavit Attached RMH/mks
)
cc:
Director Division of Reactor Operations Inspection Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. G.
G. Rhoades U.S. Nucl'ear Regulatory Commission P.O.
Box 52, Shickshinny, PA 18655 Mr. L. D. Narrow U.S. Nuclear Regulatory Commission 631 Parsec Avenue King of Prussia, PA 19406