ML19345A454
| ML19345A454 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/19/1976 |
| From: | Johnson W Office of Nuclear Reactor Regulation |
| To: | YANKEE ATOMIC ELECTRIC CO. |
| References | |
| 740219-01, 740219-1, WYR-76-20, NUDOCS 8011210619 | |
| Download: ML19345A454 (7) | |
Text
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Sp slem:nt No. 7
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Tel: phone 6l7 366-90ll
@,atory Docket Eilg 710 390 0739 YANKEE ATOMIC ELECTRIC COMPANY
.N 20 Turnpike Road Westborough, Mossochusetts 01581 KEE 6.{ X February 19, 1976
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United States Nuclear Regulatory Commission 6
k'ashington, D.C. 20555 O
um
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Attention: Office of Nuclear Reactor Regulation k4r
Subject:
Core XII Technical Specification D.2.c h
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CD,
References:
- 1) License No. DPR-3 (Docket No. 50-29)
- 2) Proposed Change No. 125, Supplement No. 6 (December 29, 1975)
- 3) Amendment No. 22 to Facility Operating License No. DPR-3, (January 20, 1976)
- 4) Amendment No. 21 to Facility Operating License No. DPR-3, December 4, 1975.
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following modifi-
~
cations to Appendix A to the Technical Specifications.
PROPOSED CHANGE:
Remove pages 54, 54a from Core XII Performance Analysis, reference 3, incorporated in Appendix A of the Technical Specifi-cations and replace them with the attached pages 54, 54a, 54b and figures 8-4 and 8-5.
REASON FOR CHANGE:
A constant multiplier to account for xenon redistribution was included in the Technical Specification of References 2 and 3.
A plant test and a series of detailed caleu:stions have now been performed which demonstrate that a burnup dependent multiplier is more appropriate, as given in item e of the proposed Technical Specifications.
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United States Nuclear Regulatory Commission February 19, 1976 Attn: Office of Nuclear Reactor Regulation Page Two SAFETY CONSIDE%TIONS:
Based on the considerations in Amendments 21 and 22 (References 3 and 4) it is concluded that Core XII operation within the proposed specifications will not endanger the health and safety of the public.
This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
SCHEDULE OF CHANGE:
We respectively request review of this proposed change by the Commission as soon as practical.
Any questions regarding this proposed change should be directed to Mr. Richard J. Cacciapouti at our Engineering Office, 20 Turnpike Road, Westboro, Massachusetts, 01581, (617-366-9011, Extension 2824).
Respectfully submitted, YANKEE ATOMIC ELECTRIC COMPANY W. P.
ohnson Vice President COMMONWEALTH OF MASSACHUSETTS)
)ss.
COUNTY OF WORCESTER
)
Then personally appeared before me, Wendell P. Johnson, who being duly sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company; and that the statements therein arc true to the best of his knowledge and belief.
9 a~ 4 wm Armand R. Soucy
. Notary Public My Commission Expires September 9, 1977
(=-
( w Tegulatory Docket Q
8.0 PROPOSED CHANGE
S TO TECHNICAL SPECIFICATIONS It is requested that the following revisions be made to the Technical Specifications.
ggw..g ggM@th Section B.
DESIGN SPECIFICATIONS i... w c. -
Add the following paragraph:
"3.
The Performance Analysis for the current reload core is incorporated as a part of these technical specifications. The analysis presented in the FSAR for Core XI forms the basis for the reference core performance analysis".
Section D.
OPERATING PROCEDURES AND RESTRICTIONS 2.
Operating Limits c.
Thermal Revise paragraph (1) to read as follows:
" (1)
During steady state power operation, the peak linear heat rate shall not exceed the limits shown in Figure 8-1.
With these linits, if full power cannot be attained, the allow-able fraction of full power shall be calculated for each l
fuel type as follows:
I "f"lPo Allowable Fraction of Full
=
LHGR p
where the limiting LHGR is obtained from Figure 8-1.
The peak full power LHGR shall include the followings a)
Heat flux power peaking factor, F measured using core instrumentation at a power > 10%;
b)
Effect of inserting the control bank from its position
~
at the time of measurement to its insertion limit (F )
I as shown in Figure 8-2.
The rod insertion limit is shown in Figure 8-3.
c)
The multiplier for xenon redistribution is a function of core lifetime as given in Figure 8-4.
In addition, if control rod Group A is inserted below 75 inches, allowable power may not be regained until power has been at a reduced level defined below for at least twenty four (24) hours with control rod Group A between 75 and 90 inches.
Reduced power = allowable fraction of full power times multiplier given in Figure 8-5.
Exception:
If the rods are inserted below 75 inches and power does not go below the reduced 4
h;
_ 543 -
t power calculated above, hold at the lowest attained power level for at least twenty fo' r (24) hours with cohtrol u
rod Group A between 75 and 90 inches before returning to allowable power.
d) Shortened stack height factor (1.009);
e). Measurement uncertainty (1.05):
f) Power level uncertainty (1.03);
g)
Heat flux engineering factor, F, (1.04);
h) Core average linear heat generation rate at full power (4.34 kw/ft).
These factors are multiplicative.
When operating at constant power, all rods out (ARO), with equilibrium xenon, power peaking in the Yankee Rowe core decreases mono-tonically as a function of cycle burnup. This has been verified by both calculation and measurement on Yankee cores nnd is in accord with the expected behavior in a core that does not contain burnable poison. The all-rods-out power peaking measured at any time in core life thus provides an upper bound on ARO power peaking for the rc=. int.or cf t.ht.t cycle.
Therarm o, t.h.
.c a c* pcwor peaking shall be checked every 1000 equivalent full power hours and the latest ceasured value shall be used in the computation. The only effects which can increase peaking beyond this value would be control rod insertion and xenon transients and these are accounted for in items (b) and (c).
Yankee Rowe is stable with respect to xenon, and any xenon transients which may be, excited are rapidly I
damped.
l l
The xenon multiplier in Figure 8-4 was selected to j
conservatively account for transients which can result from control rod motion at full power.
The limits on ' power level and control rod position
.following control rod insertion were selected to prevent exceeding the maximum allowable linear heat generation rate limits in Figure 8-l'within the first few hours following return to power after the insertion. With Yankee's highly damped core, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hold allows i
sufficient time for the initial xenon maldistribution to accommodate itself to the new power distribution. The restriction on control rod location during these twenty four hours assures that the return to allowable fraction of full power will not cause additional redistribution due to rod motion.
1 e
e
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54b -
.I These conclusions are based on plant tests and on calculations performed with the SIMULATE three dimension 1t1 nodal code, using methods similar to those i
described in Amendment 10.
These proposed changes describe the manner in which tore thermal perfomance will be monitored.
No other changes are required.
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50-29 am
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- N.RC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO:
NRC FROM:
Yankee Elec. Co.
6 W" OF DOCUMENT 76 Westborough, Mass. 01581 W.P. Johnson' oA1
, nvoo 2-20-76 E.cTTcn ONoTonlZED PnOP INPUY FORM NUMOER OF COPIES RECEIVED UonicmAL
- 62VNCLAS$1FIED OcoPy 1 Orig & 39 CC acscRIPTf0N Ltr requesting for-change CO App A ENctosUnc Revised & addl pages to Tech Specs Tech Specs notarized 2-19-76...trans the for Lic. DPR-3....
,}.
following: (PROPOSED CHANGE NO. 125, SUPPL #7 )
(40 cys enc 1. rec'd)
Dj
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ACKNOWLEF5l Yankee Rowe PLMT NAME.
SAFETY
~
FOR ACTION /INFORMATIOtJ ENVIRO DHL 2-21-76
'_J ASSICNED AD :
ASSIGNED AD :
(
EPJRC1! CHIP.F :
PURPLE (4 J 11 RANCH CHIEF :
I 4
{ PROJECT MANAGER:
BURGER PROJECT MANAGER :.
g LIC. ASST. :
SHEPPARD LIC. ASST. :
l INTERNAL DISTRIBUTION
.Y BEG FII.D SXSIEBS_ HAEETY PLANT MYSTD!9 rNyTnn TT'CH f
NRC PDR-HEINEMAN TEDESr'n ERNST s
I&E (2J SCHROEDEB BENAROYAAJLIARD l F- _.03.LD IMtjAS SPANGLER _J M COSSICK & STAPF Et{G_INEERING IPPOLITO j ULEC MACCAky SITE TECH J CoSE KNIGHT OPERATING REACTORS GANMILL l llAJA_11ER SIIMEIL STELLO SN PP l HARLESS PAULICKI HU111AN i OPERATING TECH l PROJECT MANAGEMENT REACTOR SAFETY / EISENHUr SITE ANALYSIS DOYD R0_SS / SHAO VOLIJ1ER P. COLLINS UOy p' EAER BUNCH g IIOUSTON EuS4 M ZY / SCINENCER J. COLLINS PETERSON CHECK / GRIMES KREGER 11ELTZ y llELTEMES AT & I SITE SAFETY & ENVIRC "t$. M f8 GA ~ SKOVllOLT SALTZMAN ANA1.YSIS RilTBERG DENTON & MlU.1.ER EXTE RNAL DISTitlBUTION QO_NT ROL NUMBER ~ iR00:' HAVEN N.iTL LAB /' ' ~ l - ~ _TfDR* Greenfield, Mr ss, Nffi,14n TIC REG. V-1E ULRIKSON(ORNI.) 'h,- e nSIC LA PDR _ - ~ m b@ i' ' ( IP<a' El P[e 'L AEI.H CONSUI! RANTS h E. E.__ hcl { lShi_ f.$[h* &' '.lk i_l. e u a m Whn. Y ) Y IDL n i ~ 1 m.}}