ML17139B327
| 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: |
| References | |
| NUDOCS 8302090309 | |
| Download: ML17139B327 (5) | |
Text
REGULATORY OORMATION DISTRIBUTION 'SYSOA (RIBS)
ACCESSION NBR 8302090309 DOC ~ DATE$ 83/02/03 NOTARIZED NO DOCKET FACIL:50 387 Susquehanna St~am Electric -Stationi Unit li Pennsylva 05000387 AUTH BYNAME 'UTHOR AFFILIATION 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 NMSS/FCAF/PM')/Me~g 4i ooo.
RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB2 LA INTERNAL: ELD/HDS4 IE/DEP EPOS 35 NRR/DE/AEAB NRR/DE/EQB 13 NRR/DE/HGEB 30
'NRR/DE/MTEB 17 NRR/DE/SAB 24 NRR/DHFS/HFE840 NRR/DHFS/OLB 34 NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGN1 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)
LPDR 03 NSIC 05 NOTES oO COPIES LTTR ENCL 1
0 0
1 0
1 1
0 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
6 6
2
'2 1
1 1
1 RECIPIENT ID CODE/NAME NRR L82 Bc PERCHiRB 01 IE FILE IE/DEP/EPLB 36 NRR/DE/CEB 11 NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 3?
NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DS I/METB 12 NRR/DS I/RAB 22 04
/MIB BNL(AMDTS ONLY)
FEMA REP DI V 39 NRC PDR 02 NTIS COPIES I TTR ENCL 1
0 1
1 1
1 3
1 1
z e
1 1
1 1
1 1
1 1
1 0
1 1
1 1
1 1
1 1
1 1
0.
1 1
D 1
1 1
05000387 Qy YTOTAL NUMBER OF COPIES REQUIRED:
LTTR 55 ENCL
kI,
)I r ql]1(P
(~ sg I]
>L Jfpfflkjf I f f.'. ll Ik I
II
,>'> l
']I i (I'I I
II' 1
i'l~)
I if
)
f r
I I If f((if I II i(
II IE k r~
I
(
I I
II Ir i
I I I
- k]I J,)
II I j.l, II
~ 'llr)i i i jl'-
il A If t I,P1 g
+
1 I
11
'f(I I 1]I, k it
)I II '1
'l Xf I
i'I I ff I'I )J fj f I Ii
.J I ki f1 II t
g 1
,I I.I I'
I
~ ~
I I'r,
$ +,jl f'tf II
'I iI jrrf )>jck If I
fi i
k ']lf l]lick
>l') ~<'I g I')IIXP Pill(
g ar I'c, I]I ($
'0 i
Ill'I I
ki 5h Ji Js JI
'I I
11 "II,>>X ff I
I I
jf 5r P
I' l 'I PI 4
I'f J(
I tffi rk I
k 1
f I it,]'1 w
I,
(
IiI it l(
I" f
i Jf, JII I
I I
g I
, i,k,]if, i 'l f
I I
I JI.
I'I f
I 3t I,I
)
( 'I
')J Ill JI n
II If
~-
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',
and Table 3.3.6-2 Pro osed Chan e:
Revise per Attachment A (3 pages)
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
0 t
lf
FEB 03 1983 Page 2
SSES PLA-1506 ER 100450 File 841-8 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