ML18057A495
| ML18057A495 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/19/1990 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18057A494 | List: |
| References | |
| NUDOCS 9010050114 | |
| Download: ML18057A495 (6) | |
Text
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- CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I. Changes A.
In Section 1.1 under Definitions, delete the "Interior Fuel Rod" section and all references to "Interior Rod" for the definition of t.H T
Total Radial Peaking Factor.
Replace "F 11 with "F " for Total r
r 1
Radial Peaking Factor and add "Local peaking is defined as the maximum ratio of the power in an individual fuel rod to assembly average rod power." to the definition of Total Radial Peaking Factor.
B.
In Section 2.1 under Basis, add "The MDNBR analyses are performed in accordance with Reference 6" at the end of the last para~raph.
C.
In Section 2.1 under References, add 11(6) XN-NF-82-2l(A), Revision 111 to the list of references.
D.
In Section 2.3 under Specification, replace the equation "Pvar =
1563. 7(QA) (QR1) + 12.3 (Tin - 6503.4" with "Pvar = 2012(QA)(QR1) +
17.0 (Tin> - 9493", and replace the constants "-0.691" with
- "-0.720", 111.058 11 with 111.028", "-0.653 11 with "0.62811,
11-0.15611 with
"-0.100", "0.521" with "-0.33311,
111.085 11 with 111.067", 11-0.15611 with
"-0.100", "+0.162" with "+0.200", 110.22611 with "+0.375", 110.964 11 with "0.925", "+0.162 11 with "+0.200", "+0.544" with "+0.565 11 in the QA equations.
The final TM/LP equation should be as follows:
Pv~r = 2012(QA)(QR1) + 17.0(Tin> - 9493 Where:..
QR1 = 0.412(Q) + 0.588
= Q QA = -0. i20 (ASI) + 1.028
= -0.333(ASI) + 1.067
= +0.375(ASI) + 0.925
= 1~085 when Q < 0.0625 Q ~ 1.0 Q ) 1.0
-0.628 ~
-0.100 ~
+0.200 ~
Q =
ASI ASI ASI Core Power Rated Power
< -0.100
< +0.200
~ + 0.565 E.
In Section 2.3 under Basis, replace "li2%" with "115%".
Replace "ANF-~7-150(NP), Volume 211 in References 1, 4, and 11 with OC0990-0073-NL02
2 "ANF-90-078", replace "XN-NF-77-18, section 3.8" in Reference 8 with "ANF-90-078, section 15.1.15" and delete Reference 12 (see page changes).
')
F.
In Section 3.1.1 under Specifications, replace, in item c, 11124.3 X 106 lb/hr" with "140. 7 X 106 lb/hr", replace, in item g, the Tinlet equation with "Tinlet
~ 542.99 +.0580(P-2060) + O.OOOOl(P-2060)**2
+ l.125(W-138) -
.0205(W-138)**2".
Also, replace Figure 3.0 with an updated Figure, and replace all references to 11130 M lbm/hr" with 11150 M lbm/hr".
G.
In Section 3.1 under Basis, replace "124.3 X 106 lb/hr" with "140.7 X 106 lb/hr," replace~et equation with "Tinlet
~ 542.99 +
.0580(P-2060) + O.OOOOl(P-2060)**2 + l.125(W-138) -
.0205(W-138)**2",
replace all references to "lJO M lbm/hr" with "150 M lbm/hr", and update References 4 and 5 with the new basis report ANF-90-078 (see changed pages).
H.
In Section 3.10.8 under Basis, replace "Reference 1 and 2 11 with "Reference 111, replace the superscript "(3)'_' following "violated'.'
with a "(l)" superscript and replace the superscript "(2)" following "analysis" with a 11 (1) 11 superscript (see page changes).
I. In Section 3.10.8 under References, replace "XN-NF-77-18 11 with "ANF-90-078" and delete References 2 and 3.
J.* In Section 3.12 under References, replace "ANF-87-150(NP), Volume 2" with "ANF-90-078".
K.
L.
M.
In Table 3.23.2, Radial Peaking Factor Limits, replace the 216 "Ft.H 11 assembly FA "l.50 11 with "1.57", replace "Interior" with "Peak",
r,, r with "Fr, 111.70" with 111.92", and 111.73 11 with 111.92".
r In Section 3.23.2 under Limiting Condition for Operation, replace II t.H,,
II T,,
all references to F
with F r
r In Section 3.23.2 under Basis, add the following paragraph; "The radial peaking is limited to those values used in the LOCA analysis.
Since the LOCA analysis limits the magnitude of radial peaking, Table 3.23-2 explicitly contains these limits."
t.H N *. The Section 4.1-9.2.1 under Surveillance Requirements replace "Fr*
11 with "F ".
r OC0990-0073-NL02
,...;;:/
3 II. Discussion AH In change A, the Interior *Fuel Rod F limits are removed from Technical Specifications in Section l because, for Cycle 9, the LOCA
'analysis bounds the minimum DNBR event*. The LOCA analysis is limited by the peak fuel rod peakip.g factor, F;.
The definition of "Interior fuel Rod" has been deleted since it is no longer used.
In change B, the Basis of Section 2.1 is cµanged because Cycle 9 contains f{iel.using both bi-metallic spacers and High. Thermal Performance (HTP) spacers.
Because of this mixed core arrangement, the MDNBR analysis performed for Cycle 9 utilizes 'ANFs PWR.. Thermal Margin Methodology for Mixed Core Configurations (XN-NF-82-2l(A), Revi~ion 1).
The adjustment for the mixed core effects are discussed in the Cycle 9 tra.nsient analysis report ANF-90-078,. (*Attachment 4).
In change C, reference 6 i~ added to q~c~ion 2.1 because it is the*.
report that' documents* the methodology used to perform the MJ)NBR
- - analysis *.
In change D; the changes to the Section 2.3 Specification update the constants to the TM/LP equat_ion *for Cycle 9.
The development of the TM/LP is a step-by-step procedure as described in section 15.0. 7~2.2 of*
ANF-90-078.' The* first function derived, QA, is the axial shape function and coirectJ'the TM/LP for variations in power with the axial shape index. (ASI).at a constant DNBR value.
The radial.peaking function, QR1, accounts for the changes in slope of the core protection limit lines with radial peaking and hot leg stratifi~ation. The last step is deriving the coefficients a, 8 and y.
Adjustments _were 'made. 2t~o~ the, trip coefficients to ensu_re that the t:rip conservative],.y bounds the core protection limits. *Throughout this deveiopment, the various uncertainties ~re applied to assure that the final TM/LP function is
_conservative.
In change* E, the changes to.the Basis for Section 2.3 are a result of the uncertainty on the Variable High Power Trip (VHPT) setpoint being increased from 5.5% to 8.5% for Cycle 9 as described in Section 15.0.7.3 of 'ANF-90-078 and also replacing the Cycle 8 basis report (ANF-87-150(NP), Volume 2) and the steam line break fuel analysis report XN-NF-77-18 with th~ new basis report ANF-90-078~
Change F, Section 3.1 Basis, and change G, *reflect the Cycle 9 changes which include.the replacement of the* steam generators with a lower tube plugging level (assumed to be 15% in the.transient analysis report ANF-90-078) compared to the 29.3% tube plugging ~ssumed for Cycle 8.
This will result in an increased nominalprimarT coolant (PCS) flow which provides additional thermal margin.*
The inlet equation and the basis is changed to reflect this additional margin.
The ASI LCO was also updated to increase the ASI operating window between 70%.and 25%
power.
Therefore, to meet the assumptions of the Cycle 9 safety OC0990-0073-NL02
4 analysis a measured flow of greater than 140.7 X 106 lbm/hr corrected to 532°F must be achieved.
The development of the T.
equation as a result of the fuel changes and increased flow froffintfi~ new steam generators is described in section 15.0.7.1 of. ANF-90-078.
Changes H, I, J, K, L, Mand N are self explanatory.
III. Analysis of No Significant Hazards Consideration The proposed Technical Specification changes are required for,Cycle 9 power operation and include changes to the RPS setpoints, LCOs, Bases, and References.
These changes are a result of changes to plant equipment, fuel design and the fuel management scheme* for Cycle 9.
These proposed changes require that Palisades Design Basis Accidents be reviewed to verify that the following Specified* Acceptable Fuel Design Limits are not exceeded:
- 1.
The fuel shall not experience centerline melt (21 kw/ft);
2~ The aeparture from nucleate boiling ratio (DNBR) shall bave a minimum allowable limit such that there is a 95% probability with a 9.5% confidence level that departure from nucleate boiling (DNB) has not occurred (XNB DNBR of 1.17, ANFP DNBR of 1.15).
Adyanced.Nuclear Fuel's Cycle 9 Standard Review Plan Chapter 15 Events Review (ANF-90-04~) summarizes the events that are required to be reanalyzed for Cycle 9 and which remain bounding.
The proposed Technical Specifications RPS Setpoints and LCOs are determined using.
- approved methodology.* The T LCO which provides protection against DNB during limiting Anticipa!~~eOperational Occurrences (AOOs) is used to dev:elop the initial conditions used in the. transient analysis *
(ANF-90-078) with the TM/LP trip included in the transient analysis and the VHPT factored into the TM/~P development.
The higher radial peaking factors which are limited by the LOCA analysis performed in Cycle 8 are used in determin~ng the RPS setpoints and LCOs and in a bounding MDNBR analysis that is performed for both Cycle 9 fuel types.
Consumers Power Comp~ny finds that activities associated with"this Change Request include no significant hazards;* and accordingly, a no significant hazards determination per 10CFR50.92(c) is justified.
The following evaluation supports the finding that the proposed change would not:
- 1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The effect of these changes on previously evaluated events (Standard Review Plan Chapter 15 events) has been thoroughly evaluated, class-ified (ANF-90-041) and, where appropriate, reanalyzed (ANF-90-078).
The conclusion of this classification, evaluation and reanalysis is that the effect of these changes on accidents previously evaluated are OC0990-0073-NL02
_J bounded by existing analyses; or, new analyses demonstrate that acceptance c.riteria are met for each of the reanalyzed events.
Therefore, there is no increase in the consequences of previously evaluated accidents.
Since hardware must. meet design criteria and no operating limits have been changed above analyzed values, there is no increase in the probability of an accident previously evaluated.
- 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated.
5 The proposed changes do not permit a different method of operations, but only allow operations to be modified to take advantage of improved equipment and fuel design while meeting analyzed acceptance criteria.
Therefore, no possibility of a new or different kind of accident is created.
- 3.
Involve a significant reduction in the 'margin of safety.
The existing margin of safety is provided by existing accei:>>tance..
cri.teria.
The effects of the proposed changes have been -thoroughly analyzed and do not cause the existing acceptance criteria to be exceeded.
Thus, the margin of safety is not reduced.
IV.
Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request arid has determined that this chan.ge does not involve an unreviewed safety question and, there'fore, involves no significant ha'zards consideration.
This change has been reviewed by the Nuclear Safety Services Department and founq to involve no unreviewed safety question if the specific Cycle 9 changes as listed in S.ection 1.0 of ANF-90-041 are completed with no unreviewed safety questions identified *. If an tinreviewed safety questions is identified with*regard to the related modifications, the NRC staff w.ill be notified.
A*copy of this Technical Specification.Change Request has been sent to the*State of Michigan* official designated to receive. such Amendments to the Operating License.
OC0990-0073-NL02
J
- )
CONSUMERS POWER COMPANY To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.
B~
David Sworn and subscribed to before me this 19th day of September 1990.
Beverly A Avery, Notar Public Jackson County, M chigan My commission expires December 7, 1992
- OC0990-0073-NL02 6