ML19312C907
| ML19312C907 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/07/1976 |
| From: | Parker W DUKE POWER CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19312C908 | List: |
| References | |
| NUDOCS 8001140571 | |
| Download: ML19312C907 (4) | |
Text
_ _ _ _.-
U.S. NUCLL AH HLGOL AT OHY COMMI.340N DOCKLT NUMUCft 4 y rjtj 50-273 Nr C DISTICI UTION ron
~-
FliOM:ITJEE POWER CO DATc or ooCUutnT
~
& ' C 'V1:mHE CHARLOTTE, NC 5-7-76 l%
W 0 PARKER, JR oATE ntecivco 5-10-76 yttiTon M"oTonozco enoP BNPUT FORM NUMDEH OF CoPILS HECElVEo 3 SIGN (bH s GIN AL.
UNC L ASSI F IE o 42 CC = 45 W/ ENCL 2 OCorv E N CLOGU RE oL 5Clur TION LTR NOTOP! ZED 5-7-76....REF THEIR SUH4ITTA' "
A'ITACID'ENT #1....PROPOS,ED TsCH $PEC RSVISOINS L
2-25-76 PERTAINING TO OCONEE UNIT 2, CYCLE TO SUPPORT l0C0!Q 2, CYCLE 2 OPERATION..
2 REL0/iD PEPORT...... TRANS 'I1E FOLIDWING....
EABCOCK & WIIf0X' OCONEE UNIT 2, cycle 2 RELOAD REPORT REVISION fl ITfD APRIL 1976.......
~'
s
\\
Y, h0 f5f Y L - ?- ?
go, l f
I l.
PLANT NAME: OCONEE 42...
~,7 p-r9 - --- TfW' 4.U-._1.v ii__._r_,U.;/
SAFETY FOR ACTION / INFORM ATION ENVIRO 5-12-7b RKE.
ASSIGNED AD :
h ASSIGNED AD :.
f BRANCH CHIEF d6 )
l Y u 0 P L.E BRANCH CHIEF :
{(
Pk}0 LECT l'.ANAGZi{
l PROJECT l'ANAGER :
~
})
LIC. AfST. : ( ~] )
f Q pph @
LIC. ASST. :
1 I
I INTERNAL DISTillBUTION l
PLANT SYSTFl!R FmrTon 'rven 6 Q J.G_ FILED SJ_SIEMS__SAEETY M
NRC_PDR HEINEMAN Trn RCO ERNST M
I & _E_( J -)
SCHROEDER BENAROYA BAIMRb KJ ELD LAIJias SPANGLER GOSSICK & STAFF EN(;QTEERING IPPOLITO SITE TECH MIEC MACCAgy CAS.E KNIGHT OPERATING REACTORS CAMMILL linh'A_UER SIINEIL STELLO STEPP HARLESS PAULICKI HUUiAN OPERATING TECH PROJECT MANAGE:IENT REACTOR SAFETY Y
EISENHIrr SITE ANALYSIS
}
BOYD ROSS 4
SiiAO VOLLMER l
P._ COLLINS NOVAK V
BAER BUNCH HOUSTON RO'S'ZTOCZY 4
SCHWENCER
'/
J. COI. LINS PETERSON CllECK V
CRIMES KREGER liEllrZ o n AnM in !!
s lii[LTEMES AT & I SITE SAFETY & M
@')
blW!HUc!hNil%\\\\l,
~
inh h\\ W)u@ # "
SKOV110LT SALTZMAN ANALYSIS RITrBERG DENTON & Mly.I.Ek * "
~-
EXlERN AL DISTittuu TlON CONTROL NUMBER
_I.PDR;WI M A M E U
!!5TL LAn UR00KitAVEN NATL LAB
/
I K
ULRIKSON(ORML) hk$
4
~
R _ NSIC IA PDR ASI.n CONSULTANTS o u v i 19 n nn.
2
.. ACHS HOLDItIGb)l31K..
l)I'H1: l'O W i;If COM PAN Y l'e>w me ni n nm.
m som n Cui in n Si ni :. Cnunon t. N C wou o n e,-, e e n u. s.
May 7, 1976 QU ' Q '70
- i+.
e s... m n m hTh m.n S/7M
%tu pg7 r
M3d610Ty D00.M 'A -
Y Mr. Benard C. Rusche, Director Of fice of Nuclear Reactor Regulation "d
S S. Nuclear Regulatory Commission
\\' D U.
Washington, D. C.
20555 ff j
g v !_
VM1 Attention:
Mr. R. A. Purple, Chief OV
,'p$#y;ll7ott }
Operating Reactors Branch No. 1 Re: Oconee Unit 2 b
g Docket No. 50-270 D
4
Dear Sir:
By letter of February 25, 1976, Duke Power Company submitted proposed Technical Specifications revisions to permit Cycle 2 operation of Oconee 2 and supporting documentation (BAW-1425, "Oconee Unit 2, Cycle 2 Reload Report") which described the reload core, detailed mechanical data on the reload fuel, nuclear and thermal-hydraulic design data, and accident and transient analyses. These reload design analyses and Tech:
tions were based on the originally planned 460 EFPD Cycle 1 oper ti cal Specifica-Cycle 1 operation, however, was terminated at 440 EFPD, and as a result a
on.
the burnup distribution in batch 2 and 3 fuel assemblies which are t remain in the core for Cycle 2 operation will be different o
from that assumed in the reload analyses.
The Cycle 2 core design has now reanalyzed with a new burnup distribution of the once-burned fuel assemblies been Based on this reanalysis certain core physics parameters and some Technic l Specification limits are to be revised.
a In addition, at to determine the effects of fuel rod how on Cycle 2 operation of Oth This analysis has beer performed using methods and procedures employed for conee 2.
the rod how analysis of Oconee 1, Cycle 3 (see letter of February 27
[
and its enclosures).
The analysis indicates that a possible power spike of 1976 k
1.6% may occur as a result of rod howing during Cycle 2 operation based on a j
95% confidence level and a probability that less than one rod in j m core will exceed the given power spike factor.
In order to evaluate the impact of the fuel rod bowing on DNBR, an analysis i
was performed with the COBRA III-C code to determine the effect of the flow area reduction of the hot channel resulting from rod bowing into that channel.
The results demonstrate that rod bow of the magnitude predicted 5
is adequately compensated for by the flow area reduction factor employed in the hot channel analysis.
Rod bow away from the hot channel was also analyzed.
In this analy
.s the effect of a power spike was added to the 1
4757 o
t Mr. Benard C. Rusche Page 2 May 7, 1976 hot rod in the area of minimum DNBR.
This analysis also demonstrated that the cutrent Oconee 2, Cycle 2 DNBR restfits conservatively account for the offccts of fuel rod bowing.
The impact of the rod bow power spike on limiting linear heat rate criteria (namely, central fuel melt-kw/f t taken into account by reducing appropriate sllowable limits. limit and LOCA-kw/ft limit) contains the revised Technical Specifications limits for Oconee 2, Cycle 2 taking into account the change in the burnup distribution of batch 2 and 3 fuel and fuel rod bowing effects.
~ consists of Revision 1 of Babcock and Wilcox's report BAW-1425 incorporating the revised physics parameters and other changes.
i By letters dated March 16, 1976 it was reported that Duke Power Company had been appraised of damage to the reactor vessel surveillance holder tubes which had occurred in another Babcock and Wilcox reactor.
In order to minimize the possibility of damage to the Oconee 2 surveillance holder tubes, the reactor vessel surveillance capsules have been removed and the surveillance holder tubes will be removed from the reactor vessel for Cycle 2 operation.
Oconee 2 has currently accumulated 1.21 effective full power years of exposure for an equivalent capsuleirradiation of 2.90 effec-tive full power years, since the capsule receives 2.4 times the exposure of the inside 1/4 wall thickness (1/4T) location of the reactor vessel beltline.
Since operation at the end of Oconce 2, Cycle 2 will result in a total exposure to the reactor vessel of 2.04 EFPY, there is ample margin between the present capsule irradiation and the maximum achievable exposure at the 1/4T reactor vessel beltline location at the end of Cycle 2.
In accordance with Technical Specification 4.2.9 a type B capsule removed from Oconce 2 during the present outage will be analyzed as part of the Reactor
'l Vessel Surveillance Program.
Pursuant to 10CFR50, 550.12, an exemption from the requirements of 10CFR50, Appendix H, Section II.C.2 is requested to permit the operation of Oconee 2 j
Cycle 2 with the reactor vessel surveillance specimens removed from the reactor vessel.
It is also requested, pursuant to 10CFR50, 550.90, that the Oconee Nuclear Station Technical Specifications be revised to indicate that the specir:ns will be removed from thereactor vessel for Cycle 2 opera-tion and that the surveillance withdrawal schedule will be revised prior L
to Cycle 3 operation.
The proposed Technical Specification replacement j
page is in Attachment 1.
It is considered that the operation with the f
reactor vessel surveillance specimens removed will not be inimical to the health and safety of the public.
Oconce 2 is scheduled to resume operation on June 7,1976 following removal of the surveillance holder tubes and refueling.
Is is therefore requested h
that t attached Technical Specifications be approved as soon as possible.
V y truly yours,
/1 s d.
u William O. Parker, Jr.
I r
i i
i Mr. 1;enard C. Rusche Page 3 May 7, 1976 i
WILLIAM O. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authoriz'ed on the part of said Company to sign and file with the Nuclear Regulatory Commission this request for amendment of the Oconee Nuclear Station Facility Operating Licenses DPR-38, DPR-47 and DPR-55; and that all statements and matters set forth therein are true a d correct to the best of his knowledge.
1 i
f.
i U.tl__ d.
\\
w
/
William O. Parker, Jr., Vi'ed President i
i i
ATTEST:
1 I
s i.
(?.
~ V., m f'
l Dorothea B. Stroupe Assistant Secretary a
Subscribed and sworn to before me this 7th day of May 1976.
14 )
> t2d i
hWrary Public My Commission Expires:
bA/w $,(/ M77 I'
-.,