ML20154F050
| ML20154F050 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/09/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154F053 | List: |
| References | |
| NUDOCS 8809190232 | |
| Download: ML20154F050 (9) | |
Text
_ _ _.
- #pska a%q,'o UNITED STATES 8'
Ig NUCLEAR REGULATORY COMMISSION a
.a WASHINGTON, D, C. 20555
's,..... g VERMONT YANKEE NUCLEAR POWER CORPORATION
,00CKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.10S License No. OPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated May 23, 1988 as supplemented l
August 15, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compi.iance with the Comission's regulations; D.
The issuance of this ' amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i
been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-?8 is hereby amended to read as follows:
)
i I
1 8809190232 geo999 hDR ADOCK 05000271 PDC q
I
(
2 (B) Technical Specificatiens j
The Technical Specifications, contained in Appendix A, as revised l
j through Amendment No.108. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical l
Specifications, c
i 3.
This license amendment is effective 30 days after the date of issuance.
t FOR THE NUCLCAR REGULATORY COMMISSION l
D Lv Richard H. Wessman, Director j
Project Directorate !.3 i
Division of Reactor Pro.iects 1/11 i
Attachment:
3 i
Changes to the Technical Specifications Date of issuance:
September % 1980 i
i a
i l
l l
l l
l i
r
z ATTACHMENT TO l.iCENSE AMENDMENT NO.108 FACILITY OPERATING LICENSE NO. OPR-28 3
DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 180a 180a 180b 180b 180f 180f 180-n?
180-nP 189 189 t
i i
I l
[
- Indicates new page
. - -. ~
. _ = _ _ _. _ =
~
- .1 VYNFS LIM; TING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREfENTS l
3.11 REACTO? MJEL ASSEMBLIES 4.11 REACTOR FUEL ASSEMBLIES Applicability:
Applicability:
The Limiting Conditis,ns for Operation associated The Surveillance Requirements ap91y to the with the fuel rods apply te these parameters which parameters which moaltor the fuel rod operating monitor the fuel rod operating conditirms.
conditions.
Objective:
Objective:
The Objective of the Limiting Conditic,ns for The objective 9f the Surveillance Requirements is Operation la to assure the performance of the fuel to specify the type and frequency of surveillance rods.
to be applied to the fuel rods.
Specifications:
Specifications:
A.
Averas.e Planar Linear Heat Generation Rate A.
Average Planar Linear Beat Generation Rate (APLHCR)
(APLNCR)
During steady state power operatice, the The APLNCE for each type of fuel as a APlJICR for each type of fuel as a function of function of average planar exposure staall be average plaaar exposure shall not exceed the determined daily during reactor operation at limiting values shown in Tables 3.11-1A 1251 rated thermal power.
l through J.
For single recirculation loop operation, the limiting values shall be the values from Tames 3.11-1B through E and j Table _ 3.11-1C through J listed under the heading "Single loop Operation." These Salues are obtained by multiplying the values for two loop o r ration by 0.83.
If at any time during steady-steate operation it is determined by normal surveillance that the limiting value for APLHCR is being exceeded, action shall l>e initiated within 15 minutes W
to restore operation to within the prescribed Amendment No. H. N. H IN, 108 180a
~
~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l imi "6s.
If the APLHCR isnot returned to within prescribed limits within two (2) honra, the reactor shall be brought to the shutdown conditions within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
B.
Linear Heat Generation Rate (LHCR )
B.
Linear Heat Generation Rate (LHCR)
During steady state power operation, the The LHCR as a function of core height shall linear heat generation rate (LHCR) of any rod be checked daily during reactor operation at in any f uel assembly at any axial location 225% rated thermal power.
stuill not exceed the maximum allowable IJfCR l specified in Table 1.
If at any time during steady state operation C.
hinimum Critical Power Ratio it is determined by normal surveillance that the limiting value for LHC1 is being MCPR shall be (mtermined daily during reactor exceeded, action shall be initiated within 15 power operation nt 125% rated thermal powee minutes to restore operation to within the and following any change in power level or prescribed limits.
If the LHCR is not distribution that would cause operation with returned to within the prescribed limite a limiting control rod pattern as described within two (2) hours, the reactor shall *ue in the bases for Specification 3.3.B.6.
brought to shutdown condition within 36 hr.-s t s. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
Amendment No. $$, f@. 103 180b
~
s yyyys T:ble 1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:
Core Thermal Power 1664 MWt which corresponds to 105% of rated steam flow 6
Vossel Eteam Output 6.75 x 10 1bs/h. which corresponds to l
105% of rated steam flow Vessel Steam Dome Pressure 1055 psia Recirculation Line Break Area 2
for Large Breaks - Discharge 2.26 ft2 (ogg)
- Suction 4.14 ft
[
Namber of Drilled Bundles 220 i
Fuel Parameterst f
Peak Technical Initial Specification Design Minimum f
Fuel Linear Heat Axial Critical 4
Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft)
. Factor Ratio
- l A.
7D230 7x7 18.5 1.4 1.2 B.
8D219 8x8 13.4 1.4 1.2 i
C.
8D274L 8x8 13.4 1.4 1.2 D.
8D274H 8x6 13.4 1.4 1.2 E.
8D274 (High Gd) 8x8 13.4 1.4 1.2 i
F.
LTA 8x8 13.4 1.4 1.2 i
G.
8DFB289 & P8DPB289 8x8 13.4 1.4 1.2 l
l i
2.
BPSDRB299 8x8 13.4 1.4 1.2 I
l I.
BD3248 8 x SEB 1*.4 1.4 1.2 J.
BD325B 8 x 8EB 14.4 1.4 1.2 l
- To account for the 2% uncertainty in bundle power required by Appendix K.
I the SCAT calculation is performed with an MCPR of 1.18 (i.e.
1.2 divided by 1.02) for a bundle with an initial MCPR of 1.20.
l t
Amendment No. 47, 79, 20J. 108 180f L
l i
f i
VYNPS TABLE 3.11-II MAPLIGR Versus Average Planar Exposure Plant: Vermont Yankee Tuel Typet BD324B MAPLNGR (kW/f t) for Two Loop Operation Average Planar Exposure Majority Shutdown Power Peaking Natural (mwd /t)
Lat tice Marain Zone Zone Ends 200.0 11.76 11.24 11.11 11.50 1,000.0 11.90 11.42 11.83 11.30 2,000.0 12.05 11.61 11.96 11.28 3,000,0 12.21 11.85 12.15 11.33 5,000.0 12.51 12.17 12.40 11.47 7,000.0 12.63 12.54 12.63 11.61 10,000.0 la.s0 12.80 12.80 11.72 14,400.0 12.80 12.80 12.80 11.15 15,000.0 12.75 12.74 12.74 11.07 20,000.0 12.07 12.05 12.06 10.29 25,000.0 11.41 11.39 11.40 9.50 l
35,000.0 10.14 10.12 10.12 7.93 43,360.0 8.80 8.73 8.74 4.66 l
50,000.0 6.08 5.99 6.02 Source: NEDO-21697, August 1977 (Revised) j MAPLHCR (kW/f t) for Sin 11e Loop Operation
- j Average Planar Exposure Majority Shutdown Power Peaking Natural (mwd /t)
La t tice Martin Zone Zone Ends 1
200.0 9.76 9.32 9.71 9.54 1,000.0 9.87 9.47 9.81 9.37 2,000.0 10.00 9.63 9.92 9.36 3,000.0 10.13 9.83 10.08 9.40 5,000.0 10.38 10.10 10.29 9.52
~
7,000.0 10.48 10.40 10.48 9.63 10,000.0 10.62 10.62 10.62 9.72 14,400.0 10.62 10,62 10.62 9.25 15,000.0 10.58 10.57 10.57 9.18 J
20,000.0 10.01 10.00 10.00 8.54 25,000.0 9.47 9.45 9.46 7.88 35,000.0 8.41 8.39 8.39 6.58 43,360.0 7.30 7.24 7.25 3.16 50,000.0 5.04 4.97 4.99 2
MAPLRGR for single 1 cop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.
f Amendment No.108 180.n7 i
i
J f
VYNPS f
TABLE 3.11-1J MAPLHCR Versus Average Planar Exposure Plant: Vermont Yankee Fuel Type BD326B MAPIRGR (kW/f t) for Two Loop Operation Average Planar Exposure Majority Shutdown Power Peaking Natural (mwd /t)
Lattice Marain Zone Zone Ends 4
200.0 11.00 11.35 11.76 11.50 i
1,000.0 11.86 11.42 11.79 11.30 2,000.0 11.97 11.56 11.88 11.28
[
3,000.0 12.10 11.74 11.99 11.33 5,000.0 12.48 12.16 12.33 11.47 7,000.0 12.69 12.66 12.69 11.61 10,000.0 12.90 12.90 12.90 11.72 14,400.0 12.90 12.90 12.90 11.15
)
15,000.0 12.84 12.82 12.82 11.07
)
20,000.0 12.14 12.12 12.12 10.29 i
25,000.0 11.46 11.44 11.45 9.50 35,000.0 10.17 10.15 10.16 7.93 43,360.0 8.94 8.87 8.91 4.66 l
50,000.0 6.25 6.17 6.22 Soareet NEDO-21697, August 1977 (Revised)
MAPLHCR (kW/f t) for Sinzie Loop Op'eration*
Average Planar Exposure Majority Shutdown Power Peaking Natural
)
(mwd /t)
Lattice Martin Zone Zone Ends 200.0 9.79 9.42 9.76 9.54 j
1,000.0 9.84 9.47 9.78 9.37 2,000.0 9.93 9.59 9.86 7.36 i
3,000.0 10.04 9.74 9.95 9.40 3
5,000.0 10.35 10.09 10.23 9.52 F
7,000.0 10.53 10.50 10.53 9.63 t
10,000,0 10.70 10.70 10.70 9.72 14,400.0 10.70 10.70 10.70 9.25 15,000.0 10.65 10.64 10.64 9.18 i
20,000.0 10.07 10.05 10.05 8.54 i
25,000.0 9.51 9.49 9.50 7.88 j
35,000.0 8.44 8.42 8.43 6.58 i
43,360.0 7.42 7.36 7.39 3.86 50,000.0 5.18 5.12 5.16 i
MAPLHGR for single loop operation is obtained by multiplying KAPLHGR for two loop operation by 0.83.
?
l l
Amendment No.108 180-nB l
1 l
I i
I I
v--, -, - - -. _.
,,_.-_,n_n.....-
,n.
.,.,y..,
en
,.,,.,___,._,__-.__.._._-_,n__--.m
_ _ _ ~ _..
~ _. _ _
i e
VYMPS
~.
i 5.5 Spent and,New Fuel Storage A.
The new fuel storage facility shall be such that the ef fective smultiplication factor (K,gg) of the fuel when dry.is less than 0.90 and when flooded is less than 0.95.
B.
The K gg of the fuel in the spent fuel storage pool shall be less than or equal to 0.95.
e C.
Spent fuel storage racks samy be moved (only) in accordance with written procedures which ensure that no rack modules are moved over f uel assemblies.
D.
The number of spent fuel assemblics stored in the spent fuel pool shall not exceed 2.000.
E.
The smaxismusa core geometry infinite lattice multiplication factor of any aegment of the fuel assembly stored in the spent fuel storage Pool or' the new fuel storage f scility shall be less than or equal to 1.31 at 200C.
l l
t I
l Amendment No. 37, 108 189 l
t l.., _ _ _. -, -., - - -, - - - - - - - -, - - - -,,., -
-- - - - - - - - - - = ~ ~ -, - - - - - - ~
- ~ ~ - - ' ~ - " ~ ~ ' ~ - ~ ' ~ ~ ' ' '
' " - ' ' ' ' ~ ~ ~ ~ ^ ~ ~ ' " ' ~
'