ML17139A153

Provides Response to Shielding Study Questions,Per NUREG- 0737,II.B.2 Requirements.Revision for post-accident Sampling Station Will Be Submitted 810615.One Oversize Drawing Encl.Aperture Card Available in PDR

ML17139A153
Person / Time
Site:	Susquehanna
Issue date:	05/04/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Younbloood B Office of Nuclear Reactor Regulation
Shared Package
ML17139A154	List: ML17139A153 ML19347E508
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-2.B.3, TASK-TM PLA-762, NUDOCS 8105080182
Download: ML17139A153 (3)

Text

REGULATORY INFOR'RATION DISTRIBUTIOiV SYSTEM@, (RIDS)

ACCESSION NBR;8105080182 OOC ~ DATE 81/05/04 VOTARIZED: WO DOCKET FACIL:50 387 Susquehanna Steam Electric Stationr Unit 1< Pennsylva 05000 50 388 Susquehanna Steam Electric Stationr Unit 2r Pennsylva AUTH'At K AVT-"lOR Al FILIATION CURTISr V ~ 4 ~ oennsylvania Power 4 light Co ~

RKC IP ~ .VA.SK REC1PIENI AFFILIATION YOUNBLOOODiB~ J ~ Licensing Br anch 1

SUBJECT:

Provides response to shielding study questions>per NUREG-0737i II '.2. requirements. Revision d'or post accident sampling station will be submitted 810615.0ne oversize drawing enc) Aoerture card will be in POR

~ ~

DISTRIBUTION CODE: B001S COPIES RECEIVED:LTR J ENCL I SIZE:

z'. P/

TITLE: PSAR/FSAR AHDTS and Related Correspondence iVOTES:Send ILE 3 cooies FSAR 8, all 05000387 IEE 3 conies FSAR 8 all amends, amends'end 05000388 RECIPIENT COPIES REC IP IEVT COPIES ID CODE/VAMK LTTR EiVCI. IO COOK/NAi"K LTTR ENCL ACTION: A/D LICKNSNG 1 0 I.IC BR 42 BC 0 RUSHBROOKril ~ 1 0 STARKER+ 04, 1 1 INTERNAL: ACCID EYAL BR?6 1 1 AUX SYS BR 07 1 1 CHEi4l EiVG BR 08 1 CONT SYS BR 09 1 1 CORK PERF BR 10 1 1 EFF TR SYS BR12 1 1 EMKRG PREP 22 1 0 EQUIP QUAL BR13 3 3 GEOSC IKiVCKS 14 1 1 HUM FACT ENG BR 1 1 HYD/GEO BR l5 2 2 I8'C SYS BR 16'IC 1 1 IIlK 06 3 3 GUID BR 1 1 LIC QUAL BR 1 1 "ATL FNG BR 17 1 i41ECH KNG BR 18 1 HPA 1 0 iVRC PDR 02 1 1 OELD 1 0 OP LIC aR 1 1 PONER SYS BR 19 1 1 PROC/TST RKV 20 1 1 QA BR 1 1 RAO SS BR22 1 1 REAC SYS BR 23'IT 1 1 01 1 1 ANAL BR 24 1 1 CT EiVG BR25 1 1 EXTERNAl: ACRS 27 16 16 LPDR 03 I

iV8 C 05 1 1

""Y>> 1984 TOTAL NUMBER OF COPIES REQUIRED: LTTR

TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: (215) 821.5151 NORMAN W. CURTIS Vice President. Engineering & Construction 821-5381 May 4, 1981 Mr. B. J. Youngblood Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE NO. 80 DOCKET NOS. 50-387 ER 100450 FILE 841-2 PLA-762 50-388

Dear Mr. Youngblood:

This letter provides answers to questions on the shielding study done in response to NUREG 0737 requirement II.B.2. In addition, this study is being updated to account for the new post-accident sampling station required by item II.B.3.

This revision will be submitted by June 15, 1981.

guestion i From the submittal, it appears that dose rate contributions from containment direct shine were not included in the vital area dose contributions.

a) The applicant should either make a positive statement that those dose contributions from containment dir'ect shine were investigated and found negligible in comparison to the dose calculated from vital systems and equipment.

OR, b) The applicant should revise the data in the submittal to include, the ~

direct shine from containment. Revisions involve, among others, ~go< /

Table X,1.20-3, Table X.1.20-4, and wording in Section X.1.20.3.3.2. 5 I l(s uk.

PENNSYLVANIA POWER 8 LIGHT COMPANY p~~~c zl) tSz-

Mr. B. J. Youngblood Page 2

~Res ense 1 In addition to radiation levels calculated from systems and equipment containing post-accident sources, the containment direct shine was also included as an area dose contributor. Source A defined in Section X.1.20.3.2.2 of our TMI submittal was used for the containment direct shine dose calculation and credit was taken for dose reduction by existing shield walls and for distance effects.

The radiation zone maps of our TMI submittal present the dose rates in various areas of the plant at one hour after the accident due to both the system sources described in Section X.1.20.3.2.4 and the containment direct shine.

Question 2 The post-accident radiation zone maps should be revised to show the location of the Technical Support Center, Post-Accident Sampling Station, Counting Room, and if applicable, the increase of radiation fields from direct containment shine.

~Res ense 2 Post-Accident radiation zone map, Figure X.1.20-5, has been revised to show the location of the Technical Support Center. The revised figure is attached.

The post-accident radiation zone maps will be revised and submitted to show the location of the post-accident sampling and analysis stations by June 15, 1981.

As stated in Response $11, the post-accident radiation zone maps do include the containment direct shine as a contributing dose.

Question 3 Table X.l.20-4 should be revised to show the percentage of the total dose for a particular area due to the dominant system sources

~Res onse 3 Table X.1.20-4 will be revised and submitted to show the percentage 9f the total dose for a particular area due to the dominant system source by June 15, 1981.

Very truly yours, N. W. Curtis Vice President-Engineering 6 Construction - Nuclear DPM/mjm cc: R. M. Stark