GO2-86-477, Supplemental Application for Amend to License NPF-21 Changing Tech Specs Re Establishment of MAPLHGR Limits During Single Loop Operation.Two Sets of Curves for Each Fuel Type in Both Operating Conditions Proposed
| ML17278A876 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 05/22/1986 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17278A877 | List: |
| References | |
| GO2-86-477, NUDOCS 8606020222 | |
| Download: ML17278A876 (5) | |
Text
ACCESSION NBR:
FAC XL: 50-397 AUTH. NANE SORENSEN, C. C.
RECXP. NANE ADENSANiE. C.
RECULATORY ORNATION DISTRIBUTION SY f (RIDS) 8606020222 DOC. DATE: 86/05/22 NOTARIZED: YES DOCH,ET 0 WPPSS Nucleav Pv object.
Unit 2i Washington Publi c Poue 05000397 AUTHOR AFFILIATION Washington Public Power Supplg System REC IP XENT AFFILIATION BWR Pv object Div ectov ate 3
SUBJECT:
Supplemental application +or amend to License NPF-21 changing Tech Spers ve establishment of NAPLHQR limits during single loop opev ation.
Taboo sets of curves for each fuel type in both opev'ating conditions pv oposed.
DISTR19UTION CODE:
A001D COP XES RECEIVED: LTR ENCL Sl ZE:
TXTLE:
OR Submittal:
Qenev al Distv ibution NOTES'ECIPIENT ID CODE/NAf'fE BWR ADTS BWR EICSB BWR PD3 PD 01 BWR PSB COP IES LTTR ENCL 1
0 5
5 1
RECIPIENT ID CODE/NANE BWR EB BWR FOB BR*DFUTE> J BWR RSB COPIES LTTR ENCL 1
1 1
1 1
INTERNAL: ACRS ELD/HDS2 NRR/ORAS RQN5 EXTERNAL: 24X LPDR NSXC 09 03 05 6
6 0
1 0
1 1
1 1
1 1
1 ADN/LFNB
/TSCB REQ FILE 04 EQhQ BRUSKE~ S NRC PDR 02 1
0 1
1 1
1 1
1 1
1 ADO: MRR/DsRo/RaiS Rw/ 0 @gag(iii~
3i.
2 E'OTAL NUNBER OF COPIES REQUIRED:
LTTR PS ENCL
SY rr.J'~ E$'..~~luVl
".~-;XPG i&8:PT;"rt..aG<I;9",Gr.:O~QA(3
'3va't t L ago')
tto 'Qn. '~lb 2 8irtU i~.".~r,o "r i tr'.3 f <<ural dr.rk"(~A MOI'r'AK lL"~'if) 'HGfll'UA ma'rvgR ltLqquB vsMa'i yildu'l noPprtid'N l~~OKTAiJE l c~')
f'N.]Sufi:) i$l P-s~sva as t.iV, 8 i~t,ov'L ViWH
'1 ill '9'.r'rs ~ 13 64
) rtscl6
<9%
no % $ 4 2 H, g'qo 4~8'noQs wqquu l ):t'l~VUt..
o~ irrrif 8')llew'V~l"t
%a fnsmrlziLds9eo s t,";o"rq8 rl> t r'niprtotl')
rl30')
'ro3 '-av TUB io 2
ai?
Ol'JT.Aoffo toque qao I 9 Irlr'i" on p.'TU4
,4 >'!oqovq snail ibnaa pni8c t ">qo rllod rri sq>>4
- .->XX-..
laWZ...
RT.l:G3VraaSR aaK,C)V aE0C;,suan i l1)1V trATQ'.t nai >udiv8~! iG A'~vonsO
.LoNk'nrduQ
$)r) cg t trll BL~30:)
l )'>r3 HT) k P<<3 ). "8 KDHR
-~l',"AMX3GGQ GI 83 RMR GQ0 RNH t
.:<<'AHAARG 8HR RWG j r<t.37, ~iE~"-4'l
<<l'lOVA,'iu().; G'r.
8 l (r.A H!'KB !'~'rl.
E 0'l
>">>'es','1 0
E Gil33%i1GA 6:p~rT % t 'OW gal
&0 3 rfa GHR c3 0
0 E
C'0
- Jf Y.l195lfli'
<388UR4 P>>QB PG'l DRN P(l i,()
Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richiand, Washington 99352-0968 (509)372-5000 May 22, 1986 G02-86-477 Docket No.
50-397 Director of Nuclear Reactor Regulation Attn:
E.
G. Adensam, Project Director BWR Project Directorate No.
3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear,
Ms.
Adensam:
Subject:
Reference:
NUCLEAR PLANT NO.
2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS -
RELOAD LICENSE AMENDMENT (CYCLE 2),
SUPPLEMENTAL INFORMATION
- Letter, G02-86-173, G.
C. Sorensen (SS) to E.
G.
Adensam (NRC), "Request for Amendment to Technical Specifications
- Reload License Amendment (Cycle 2)",
dated February 26, 1986 The reference letter requested certain changes to the WNP-2 Technical Specifications.
In submi tting changes to Section 3/4.2.1, Average Planar Linear Heat Generation
- Rate, the Supply System incorrectly applied'irection given by Exxon Nuclear Company (ENC} for establishing MAPLHGR limits while in single loop operation.
Exxon has evaluated the GE limits as being conservative with respect to the Exxon fuel design based on their DBA LOCA analyses and supports application of the adjusted GE MAPLHGR single loop limit.
To avoid confusion in interpreting LCO 3/4.2. 1, we are proposing the usage of two separate sets of curves for each fuel type in both operating conditions.
The two sets will present the two loop operating limits for all fuel types and a separate set for single loop operation.
For GE fuel, the new graphs for single loop operation do not represent a change to previous submittals.
For the Exxon tuel a conversion factor of.77 is being applied to mathematically apply slightly more conserva-tive nodal MAPLHGR limits than applied to GE fuel.
Direct application of the GE 8CR233 fuel single loop APLHGR limit curve in monitoring MAPLHGR for ENC fuel is not possible with existing POWERPLEX software.
8606020222 860522 PDR
- DOCK 05000397 P
~ gag pro/4~1~
ggaygJgmg/~l+
00(
'C'
E.
G.
Adensam Page Two May 22, 1986
. RELOAD LICENSE AMENDMENT (CYCLE 2),
SUPPLEMENTAL INFORMATION To verify that use of the.77 multiplier applied to the ENC XN-1 fuel-would be conservative for. Cycle 2 operation when compared to the previously approved
.84 multiplier times the GE 8CR233 type fuel MAPLHGR limits applied to the ENC XN-1 fuel, a comparative set of calculations was performed.
To account for differences in Bundle Average Exposure versus Average Planar
- Exposure, a conservative axial peaking factor of 1.5 was divided into Average Planar Exposures to yield the comparative Bundle Average Exposure points.
Based on the results of these comparative calculations, the single loop MAPLHGR curve for ENC XN-1 fuel has been truncated at a
bundle average exposure of 15,000 MWD/mt.
Although this supplementary information presents more conservative limits than those previously submitted
, the Supply System has reviewed this supplementary information per 10 CFR 50.92 and determined that it does not:
1)
Involve a significant increase in the probability or consequences of an accident previously evaluated because the analyses previously performed by GE for cycle one supported extended single loop operation and the Exxon evaluation of their DBA-LOCA analyses concluded application of the GE limits for Exxon fuel was conservative.
2}
Create the possibility of a new or different kind of accident from any accident previously evaluated because the analyses is specifically designed to evaluate the most limiting accident.
3)
Involve a significant reduction in the margin of safety because the nature of the analyses and evaluation is to ensure conservative limiting conditions for operation are applied.
This change moves in a more conservative direction.
Additionally, this supplementary information has been reviewed with respect to 10 CFR 50.59 and does not represent an unreviewed safety question.
Attached are proposed technical specification pages reflecting this supplementary information.
Should you have any further questions, please contact Mr. P.
L. Powell, Manager, WNP-2 Licensing.
Very truly yours, G.
C. Sorensen, Manager Regulatory Programs PLP/MRW/tmh Attachments cc:
JO Bradfute -
NRC C
Eschels -
Revell -
BPA NS Reynolds -
BLCP&R NRC Site Inspector