ML17139B327

Forwards Application for Amend 19 to License NPF-14,changing Tech Specs to Allow Expansion of Operating Region of Power/ Flow Map for Initial Fuel Cycle & Sampling Alignment to Either Drywell or Suppression Pool

ML17139B327
Person / Time
Site:	Susquehanna
Issue date:	02/03/1983
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17139B328	List: ML17139B327 ML17139B329 ML17139B330 ML17139B331 ML20028G418
References
NUDOCS 8302090309
Download: ML17139B327 (5)

Text

REGULATORY OORMATION DISTRIBUTION 'SYSOA (RIBS)

ACCESSION NBR 8302090309 DOC DATE$ 83/02/03 NOTARIZED NO DOCKET FACIL:50 AUTH BYNAME387 Susquehanna

'UTHOR St~am

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Electric -Stationi Unit AFFILIATION li Pennsylva 05000387 CURTIS'ON ~ Pennsylvania Power 8, I.ight Co>>

REC IP ~ NAME REC IP IENT AFFILIATION SCHKENCERgA ~ Licensing Branch 2

SUBJECT:

For wards application for Amend 19 to License. NPF-14ichang n9~~

Tech Specs to allow expansion of operating region of powei /

flow map for int;ial fue) cycle 8, sampling alignment to either drywell or suppression pool. rb'p~ (

DISTRIBUTION CODE: 8001S COPIES RECEIVED:LTR g'ENCL .gD SI2E . 4'+'gg TITLE: Licensing Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES: 1cy 05000387 NMSS/FCAF/PM')/Me~g 4i ooo. oO RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME I TTR ENCL NRR/DL/ADL 1 0 NRR L82 Bc 1 0 NRR LB2 LA 0 PERCHiRB 01 1 1 INTERNAL: ELD/HDS4 1 0 IE FILE 1 1 IE/DEP EPOS 35 1 1 IE/DEP/EPLB 36 3 NRR/DE/AEAB 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 z e NRR/DE/HGEB 30 1 1 NRR/DE/MEB 18 1 1

'NRR/DE/MTEB 17 1 1 NRR/DE/QAB 21 1 1 NRR/DE/SAB 24 1 NRR/DE/SEB 25 1 1 NRR/DHFS/HFE840 1 NRR/DHFS/LQB 3? 1 1 NRR/DHFS/OLB 34 1 1 NRR/DL/SSPB 1 0 NRR/DSI/AEB 26 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CSB 09 1 1 NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 1 NRR/DSI/PSB 19 1 1 NRR/DS I/RAB 22 1 NRR/DS I/RSB 23 1 1 04 1 1 RGN1 /MIB 1 0.

EXTERNAL: ACRS 41 6 6 BNL(AMDTS ONLY) 1 DMB/DSS (AMDTS) FEMA REP DI V 39 1 D LPDR 03 2 '2 NRC PDR 02 1 1

NSIC 05 1 1 NTIS 1 NOTES 1 1 Qy YTOTAL NUMBER OF COPIES REQUIRED: LTTR 55 ENCL

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Pennsylvania Power 8 l ight Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 i 770-5151 Norman W. Curtis Vice President-Engineering & Construction-Nuclear 21 5/770-7501 FEB 03 1983 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory" Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT 19 TO LICENSE NPF-14 ER 100450 FILE 841-8 PLA-1506 Docket No. 50-387

Dear Mr. Schwencer:

The purpose of this letter is to propose two changes to Appendix A of License No. NPF-14, the Susquehanna SES Unit 1 Technical Specifications. The proposed changes are provided as Attachments A and C to this letter.

ITEM 1: Table 2.2.1-1, Specification 3.2 Pro osed Chan e:

Revise per Attachment A (3 pages) and Table 3.3.6-2 Justification for Chan e: The proposed change allows the expansion of the operating region of the power/flow map for the initial fuel cycle of SSES Unit 1. The APRM flow-biased scram and APRM rod block trip setpoints and allowable values are changed in the referenced sections to reflect this expansion.'he basis for these new limitations is contained within NEDO-22128 (Attachment B), "General Electric, Boiling Water Reactor Expanded Load Line Limit Analysis for Susquehanna Steam Electric Station Unit 1." Our review of this analysis indicates that the new Technical Specification will allow SSES Unit 1 to operate closer to the existing core operating limits but will not reduce the margin of safety as defined in the bases of the Technical Specifica-tions.

,ITEM 2: Specification 3.4.3.1 Pro osed Chan e: Revise per Attachment C Justification for Chan e: The design of the primary containment atmosphere radioactivity monitoring system allows for sampling alignment to either the drywell or the suppression pool. The suppression pool sample line is primarily for post accident monitoring; normal alignment is to the drywell in order to detect and quantify unidentified leakage pursuant to Technical Specification 3.4.3.2, The current wording (i.e. "primary containment") allows either line to serve the normal leak detection function. Such a, misinterpretation was the subject of Licensee Event Report No. 82-060/03L-0 (PLA-1456, December 23, 1982). In that report, PP&L committed to propose this change to Technical Specifications.

8302090309 830203 PDR ADOCK 05000387 P PDR I ga

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Page 2 SSES PLA-1506 ER 100450 File 841-8 FEB 03 1983 Mr. A. Schwencer We have determined these changes to be Class III in nature and have enclosed the appropriate fee pursuant to 10CFR170.

Very truly yours, N. W. Curtis Vice President-Engineering & Construction-Nuclear Attachments cc: R. L. Perch USNRC