ML20205R514

Proposed Tech Spec 5.3.1, Fuel Assemblies, Allowing for Replacement of Fuel Rods W/Filler Rods or for Vacancies If Such Replacement Acceptable Based on Results of cycle- Specific Reload Analysis

ML20205R514
Person / Time
Site:	Callaway
Issue date:	03/27/1987
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20205R494	List: ML20205R490 ML20205R514
References
NUDOCS 8704060369
Download: ML20205R514 (5)

Text

. . .

~

OESIGN FEATURES O .A:' !'! .

5.3 REACTOR CORE M h m:4-JLL 3

FUEL ASSEMBLIES E 3, g "A prelp 4

Q^'A"" *- y -

, . 0 = )_ .

5.3.1 The core shall contain 193 fuel assembli es with eac assembly containing 264 fuel reds clad with Zircaloy-4pF Each fuel rod shall have a nominal active fuel ..gth of 144 inches and contain a maximum total weight of 1766 grams uranium. h initi:1 ::r: ?:: ding she!' h:;: -29' e.--ich:: .:

-Of 2.10 ::ci; .t per::at W2Fx Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.20 weight l percent U-235.

CONTROL RCD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies shall contain a itominal 142 inches of absorber material. All control rods shall be hafnium, clad with stainless steel tubing.

3.4 REACTOR COOLANT SYSTEM DESTGN PRESSURE AND TEMPERATURE

) 5.4.1 The Reactor Coolant System is--designed and shall be maintained:

a. In accordance with the Code requirements sp'ecified in Section 5.2 of the FSAR, with allowance.for normal degradation pursuant to the applicable,Survefilance. Requirements, ,

b. For a pressure of 2485 psig, and

c. Fer a temperature of 650*F, except for the pressurizer which is 680*F.

VOLUME 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge ifne, is 12,135 ; 100 cubic feet at a nominal T,yg of 557*F.,

i 5.5 METEOROLOGICAL TOWER LOCATION.

5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

8704060369 870327 3 DR ADOCK 0500 CALLAWAY - UNIT 1 5-6 Amendment No. -338

• ULNRC-1477 Attachment 2 SAFETY EVALUATION This license amendment request proposes to revise Technical Specification 5.3.1 to allow for the replaccment of a limited number of fuel rods with filler rods or for vacancies if such replacement / vacancy is acceptable based on the results of the cycle-specific reload analysis.

The current Technical Specification 5.3.1 states that each fuel assembly shall contain 264 fuel rods clad with Zircaloy-4.

Approval of this amendment request will allow for a reduction in the number of fuel rods per assembly and replacement of defective rods with filler rods consisting of either Zircaloy-4 or stainless steel, or with vacancies. The ability to replace defe'ctive rods with filler rods or to have vacancies will permit utilization of the remaining energy in fuel assemblies.

A safety evaluation for the replacement of fuel rods will be made on a cycle-specific basis as part of the reload safety evaluation process. The core reload analysis is performed to ensure that the safety criteria and design limits, including peaking factors and core average linear heat rate effects, are not exceeded. An explicit model with each discrete rod identified is utilized to predict core performance based on actual core inventory. The core reload methodology does not change when filler rods or vacancies are used. The filler rods or vacancies in a fuel assembly that are used in a core design will be modeled as required for the specific replacement.

In addition, the sentence which addresses the maximum enrichment for the initial core loading has been-deleted. This is historical in nature and has no current applicability.

Pursuant to the above information, this amendment request would not adversely affect or endanger the health and safety of the general public and does not involve an unreviewed safety question.

-ULNRC- 14 7 7 Attachment 3 SIGNIFICANT HAZARD EVALUATION This license amendment request proposes to revise Technical Specification 5.3.1 to allow for the replacement of a limited number of fuel rods with filler rods or vacancies if such replacement is acceptable based on the results of the cycle-specific reload analysis. Union Electric Company has evaluated this change within the guidelines of the Significant Hazards Criteria of 10CFR50.92. The following evaluation is provided for the no significant hazard finding:

a) This license amendment request will allow the use of filler rods or vacancies in fuel assemblies at Callaway Plant. These fuel assemblies will meet the same mechanical, nuclear, and thermal hydraulic limits as an original fuel assembly, as described in FSAR Chapter 4.

The reload safety evaluation for each cycle will confirm that the use of a fuel assembly with filler rods or vacancies in a core design does not result in an existing design limit being exceeded. Therefore, this license amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated.

b) As discussed above, a fuel assembly with filler rods or vacancies satisfies the same design limits as an original fuel assembly. Therefore, this license amendment request does not create the possibility of a new or different kind of accident from any accident previously evaluated.

c) As discussed above, the use of a fuel assembly with filler rods or vacancies will not result in an existing design limit being exceeded. Therefore, this change does not reduce the margin of safety.

It has been determined that the use of reconstituted fuel assemblies in reload cores does not pose a significant hazards consideration. This is based on Example lii of those examples of amendments that are considered not likely to involve significant hazards considerations (48 FR 14870). Example lii states: "For a nuclear power reactor, a change resulting from a nuclear reactor core reloading, if no fuel assemblies are significantly different from those found previously acceptable to the NRC for a previous core at the facility in question are involved. This assumes that no significant changes are made to the acceptance criteria for the technical specifications, that the analytical methods used to demonstrate conformance with the technical specifications and regulations are not significantly changed and that the NRC has

previously found such methods acceptable". The analyses show that the reconstituted assemblies will meet the original _ design criteria. The analytical methods used will remain unchanged.

The amendment also deletes a sentence which addresses the maximum enrichment of the initial core. This sentence is historical and

.has no current applicability and therefore represents a purely administrative change.

Based on the above discussions, the amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated; nor create the possibility of a new or different kind of accident-from any accident previously evaluated; nor involve a reduction in the required margin of safety.- Based on the foregoing, the requested amendment does not present a significant hazard, s

ULNRC- 14 77 Attachment 4 e

Application' Fee 804 245 CHECX NUMBER 855 UNION ELECTIUC COMPANY sr.Lous.Missom 219755 TO CENTERRE BANK OF KENNETT MISSOURI 4540

"" ^" ""'

i PAY .

03 24 87 $ * * * * * *150 00 U S NUCLEAR REGULATORY ro ruc onctn or COMMISSION I Caccxs ovcR in.oool REQUIRE COUNTER $1GNATURE j 1717 H ST NW WASHINGTON DC r7-N ip- r- i

' ";;'jllil'g 'g\ N ',i THIS CHECK 20555 'iDF y,d

b'LJ' I'M '" ##8%

VOID AFTER AUTHOR (iEQ SiGNATuSE 90 DAYS . . . .

"" ="a ma*

n' 2 L 9 7 5 5 n' i:08 L 50 24 591: 84 035 L u' l

l

_ _ ._ _- ._. __ _ , . . . _ _