ML20052F593
| ML20052F593 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/10/1982 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20052F590 | List: |
| References | |
| LCA-87, NUDOCS 8205130223 | |
| Download: ML20052F593 (11) | |
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l PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER S ELECTRIC BOARD AND l
PACIFIC POWER & LIGHT COMPANY l
TROJAN NUCLEAR PLANT l
Operating License NPF-1 Docket 50-344 License Change Application 87 This License Change Application requests modification of the F
,F AH' and moderator temperature coefficient technical specifications for the Trojan Nuclear Plant.
PORTLAND GENERAL ELECTRIC COMPANY By
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B. D. Withers Vice President Nuclear Subscribed and sworn to before me this 10th day of May 1982.
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OMyCommiss h )?
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Notary Public of Orgfon
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l 8205130223 920510 PDR ADOCK 05000 P
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Trojan Nuciser Plant Rob 2rt A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 1 of 9 LICENSE CHANGE APPLICATION This License Change Application proposes revisions to the F, (z),
F H, and moderator temperature coefficient Technical Specification limits.
The Technical Specifications for the Trojan Nuclear Plant will be modified as shown in Attachment 1 and as described in the Safety / Environmental Evaluation below.
REASON FOR CHANGE The proposed revisions to the F (z), FaH, and m derator temperature coefficient Technical Specifications will result in a significant increase in fuel cycle flexibility at the Trojan Nuclear Plant.
SAFETY / ENVIRONMENTAL EVALUATION A.
Summary of Change (1) F Technical Specifications The existing F (z) Technical Specification limits will be replaced with a reference to a radial peaking factor limit report, which will be submitted to the NRC if the F limits xy need to be changed. This will eliminate the need for a Technical Specification change if the F (z) limits require revision. A sample Radial Peaking Factor Limit Report is given in Attachment 2.
s Trojan Nuclear Plant Robert A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 2 of 9 (2) F Technical Specifications AH The proposed change will modify the enthalpy hot channel factor F Technical Specification limit AH from 1.49(1 + 0.2(1-P)] to 1.49[1 + 0.3(1-P)].
This change in slope will allow a higher F at AH reduced power with no change in the full power F
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AH (3) Positive Moderator Temperature Coefficient The proposed change will revise the moderator temperature coefficient (MTC) Technical
-4 Specification limits to 10.5 x 10 AK/K/*F below 70 percent power and a MTC of 10 at or above 70 percent power. This will allow opera-tion of the Plant with a positive moderator temperature coefficient at power levels below 70 percent rated thermal power.
l B.
Effect on Technical Specifications
- 1) F Technical Specifications The F,y Technical Specification changes involve the removal of the F (z) limits from Technical l
Specification 4.2.2.2.e and their incorporation into a Radial Peaking Factor Limit Report. This change also includes the addition of Technical Specification 6,9.1.10, which requires the sub-21ttal of this report to the NRC in the event the F limits need to be changed. Since F (z)
Trojtn Nuclszr Plsnt Robert A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 3 of 9 is a surveillance limit and not the limiting condition for operation, it is reasonable to allow for revision of the F (z) limits when necessary provided suitable notification is given to the NRC.
The Radial Peaking Factor Limit Report provides a mechanism to accomplish this without the need to submit F. Technical Specification changes. Using this mechanism, then, F (z) limits could be revised while still falling into the submittal guidelines of 10 CFR 50.59.
Removal of the F (z) limits from the Tech-l nical Specifications has been accepted by the NRC for other nuclear power plants and has recently been incorporated into NUREG-0452 (Rev. 4), " Standardized Technical Specifica-tions for Westinghouse Pressurized Water Reactors". The proposed changes for Trojan dif fer slightly from NUREG-0452 (Rev. 4) in the following respects:
(a) Clarification has been added to require submittal of a Radial Peaking Factor Limit Report only if it is necessary to change the existing F values. This will elimi-nate unnecessary submittals and preclude unnecessary delays (see item b below).
The current F limits for Rated Thermal Xy Power within specified core planes shall serve as the baseline values for determin-ing if changes are necessary. These values are as follows:
9 Trojan Nuclear Plsnt Robsrt A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 4 of 9 (i)
F,y 9 71 for all core planes containing bank "D" control rods.
(ii) F g.65 for unrodded core planes.
(b) In the event that the F limits are changed, the Radial Peaking Factor Limit Report will be submitted to the NRC at least 30 days prior to cycle initial criticality instead of 60 days prior to criticality. This will preclude unnecessary delays during situa-tions in which changes to F limits are determined to be necessary relatively close to the date of initial criticality (such as during the course of a refueling outage) yet still provide the NRC with ample time to review the change.
(2) F Technical Specifications aH The proposed change in F results in the aH l
following Technical Specification changes:
(a) Technical Specification Figure 2.1-1 includes an allowance for an increase in F l
at reduced power. The proposed change replaces the equation F
= 1.49[1 + 0.2(1-P)] with H
the equation F
= 1.49[1 + 0.3(1-P)] and H
l Figure 2.1-1 has been revised accordingly; 1
xy [1 + 0.2(1-P)] in (b) The equation F
=F Xy Technical Specification 4.2.2.2.c.2 has been xy [1 + 0.3(1-P)];
changed to read F
=F xy
Troj:n Nuclear Plant Rsbert A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 5 of 9 -
FAH (c) The equation FR " 1.49[1.0 + 0.2(1-P)]
in Technical Specification 3.2.3.a and in Technical Specification 4.2.3.2.b has been changed to read FAH FR " 1.49[1.0 + 0.3(1-P)]
and Figures 3.2-3 and 3.2-4 have been revised accordingly. In addition, a typographical error in Technical Specification 4.2.3.2.b has been corrected ("3]" was changed to "31").
Westinghouse's evaluation of the core limits and axial offset envelopes has shown that no change in the overpower and overtemperature delta-T setpoints or the f(AI) function will be necessary. No changes in the reactor protection system setpoints are required as a result of the revised F 0.3 multiplier. Therefore, no aH accidents need to be reanalyzed as a result of this change.
(3) Positive Moderator Temperature Coefficient The proposed change in the MTC will result in i
changing Technical Specification 3.1.1.4.a from l
"a.
Negative, and" to f,0.5 x 10 ' aK/K/*F below 70 percent "a.
RATED THERMAL POWER
~4 f,0.0 x 10 AK/K/*F at or above 70 percent RATED THERMAL POWER".
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s Trojan Nuclear Plsnt Robert A. Citrk Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 6 of 9 Technical Specification 3.1.1.4.b, which requires a
-4 MIC that is less negative than -5.36 x 10 AK/K/*F at rated thermal power, will not be changed.
The safety analysis associated with the proposed change is presented in Attachment 3.
C.
Effect on Bases for Technical Specifications (1) F Technical Specifications i
xy The proposed change simply removes the record-ing of the F limits from the Technical Specifications; it does not delete the exist-ence of the limits nor does it affect the surveillance requirements regarding F Therefore, no changes to the Bases for Tech-nical Specification 3/. 2 are required.
(2) F Technical Specifications H
The expression 1.49[1 + 0.2(1-P)] in the Bases for Technical Specifications 2.1.1, 3/4.2.2 and 3/4.2.3 will be changed to 1.49[1 + 0.3(1-P)].
An evaluation of the core limits and axial offset envelopes showed that no changes to the overpower and over-temperature AT setpoints or the f(AI) function i
were necessary. Therefore, no other changes i
in the Technical Specification Bases are necessary.
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s Trojan Nuclasr Plant Rob 2rt A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Fage 7 of 9 (3) Positive Moderator Temperature Coefficient 2
The Bases for Technical Specification 3/4.1.1.4 states that the limitations on MTC are pro-vided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle, and that the surveillance requirements given in Technical Specification 4.1.1.4 are adequate to con-firm the MTC value.
The safety analysis presented in Attachment 3 has shown that the proposed change can be accommodated with margin to the applicable FSAR safety limits. In addition, the proposed change does not affect the surveillance requirements for the measurement of the MTC. Therefore, no changes to the Bases for Technical Specifica-tion 3/4.1.1.4 are required.
D.
Effect on FSAR (1) F Technical Specifications The proposed change modifies the manner in which the F limits can be changed in the future. The j
xy F
limits identified in FSAR Section 4.3.2.2.6 Xy sere identified as being for the first cycle only, f
and the methodology for changing these limits was not discussed in the FSAR. Therefore, no changes to the FSAR are required.
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Trojan Nucisar Plent Rsbert A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 8 of 9 (2) F Technical Specification AH The proposed change to use a 0.3 multiplier instead of a 0.2 multiplier affects the corre-sponding equations in FSAR Section 4.3.2.2.6 and 4.4.3.2.
However, since the proposed change does not require any reactor protection system setpoint changes or the reanalyses of any accidents, the underlying conclusions reached in the FSAR remain valid and need not be changed.
(3) Positive Moderator Temperature Coefficient The proposed change to allow a slightly posi-tive moderator coefficient at up to 70 percent power affects FSAR Section 4.3.2.5.7 which states that the boron concentration must be limited during operating conditions to insure the moderator temperature coefficient is nega tive. The proposed change does not affect FSAR Section 4.3.2.3.5, since it is stated in this section that "The need for a reevaluation of any secident in a subsequent cycle is con-tingent upon whether or not the coefficients for that cycle fall within the identified range used in the analysis presented in Chapter 15."
A reevaluation has been performed and the effect on the FSAR analyses is discussed in.
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Trojnn Nuclear Plant Robert A. Clark Docket 50-344 May 10, 1982 License NPF-1 LCA 87 Page 9 of 9 E.
Environmental Effect The proposed changes will not change effluent types nor increase amounts. No unreviewed environmental matter exists and there will be no significant environ-mental impact from this change.
SCHEDULE CONSIDERATIONS Prompt review and approval of this LCA is requested in order to incorporate the proposed changes in the Cycle 5 core design without impacting the resumption of power operation on July 1, 1982.
BASIS FOR DETERMINATION OF AMENDMENT CLASS This License Change Application has been determined to result in a Class III amendment in accordance with the criteria of 10 CFR 170.22. A single safety issue is involved which does 1
i not include a significant hazards consideration.
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