ML20137E888

Proposed Tech Spec Changes to Section 4.3.4.D,Pages 105 & 119 Re Matls Irradiation Surveillance Specimen Insp,Revising Specimen Capsule Withdrawal Schedule

ML20137E888
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	08/19/1985
From:	COMMONWEALTH EDISON CO.
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ML20137E871	List: ML20137E867 ML20137E888
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0500K, 500K, NUDOCS 8508260094
Download: ML20137E888 (7)

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ATTACWENT l PROPOSED ZION'APPEtOIX A TECHNICAL SPECIFICATION CHANGES T0 SECTION 4.3.4.D MATERIALS IRRADIATION SURVEILLANCE SPECIMEN INSPECTION Pages Hodified: 105 119 0500K 8508260094 PDR- 850819ADOCK 05000295 PM P

LIMITING CONDITIDN FOR OPERATION SURVEILLANCE REQUIREMENT l

3.3.4 4.3.4 D. Materials Irradiation Surveillance Specimen Inspection. (per unit)

Specimen capsules to be used in the reactor vessel material surveillance program shall be withdrawn during the refueling period either immediately-preceeding or following the Effective Full Power Years (EFPY) of unit life as follows:

CAPSULE WITHDRAWAL SCHEDULE UNIT 1 CAPSULE- CAPSULE

}

DESIGNATION REMOVAL TIME (EFPY)

T REMOVED (1.16)

U REMOVED (3.52)

X REMOVED (5.17)

Y 8.5 W,S,V,Z STAND BY UNIT 2 CAPSULE CAPSULE DESIGNATION REMOVAL TIME (EFPY)

U REMOVED (1.27)

T REMOVED (3.56)

Y 8.5 X STAND BY W,S,V,Z STAND BY 105 09030

j . '.-

j Basis 4.3.4 The surveillance' inspection program has ,

i been developed to comply with Section XI of the ASME Boller and Pressure Vessel Code and applicable addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1). The design of the plant, state of non-destructive testing technology, and access to areas to be inspected require such relief.

The Reactor Vessel Material Surveillance-Program is designed to ev'aluate the effects of radiation on the fracture toughness of reactor vessel steel based ja on the transition temperature approach and the fracture mechanics approach.

10 CFR 50, Appendix H, paragraph 11 B.1 requires that the reactor vessel material surveillance program shall meet the requirements of ASTM E185-82 such that the surveillance capsules represent end-of-11fe fluences at the reactor vessel 1/4 and wall thicknesses.

Previous capsules were removed under Amendment Nos. 62 and 59. .

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119 t

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ATTACFNENT 2 JUSTIFICATION FOR PROPOSED CHANGE Low leakage loading patterns were implemented at Zion in Unit 1 Cycle 7 and Unit 2 Cycle 6. Unit 1 Cycle 9 began operation in June of 1985 and Unit 2 Cycle 8 will end in September of 1985. This change has resulted in a reduction of the EOL fluence projections for the reactor vessel inner wall and 1/4 T locations.

The revised EOL (32 EFPY) projections for E>l MEV fluence are approximately 1.0 x 10 19 n/cm2 and 1.8 x 1019 n/cm2 for the 1/4 T and inner wall locations, respectively. WCAP 10902 contains the detailed technical basis for these' projections. 10 CFR 50, Appendix H recommends, by reference to ASTM E-185, removing the third and fourth surveillance capsules at fluences corresponding to the projected EOL values for the vessel 1/4 T and inner wall locations respectively.

Table 1 (attached) provides the capsule withdrawal history and proposed future schedule. Note that capsule U from Unit 1 and capsule T from Unit 2 correspond to the approximate EOL fluence at the vessel 1/4 T location. Capsule X of Unit 1 was removed in February of 1982 to comply with the current Technical Specifications, but is at a fluence of no particular interest to the propcsed schedule. Capsule X of Unit 2 was not removed as required by Zion's current Technical Specifications (LER 50-304/65-09).

The Y capsules are seneduled to be removed at 8.5 EFPY to provide data at approximate EOL fluence at the vessel inner wall location. These capsules contain weld metal Wedge Open Loading (WOL) specimens. Capsule X of Unit 2 is retained as a standby in the event that higher EOL fluence is indicated in the future due to changes in the core loading which may increase flux at the vessel wall, or to decisions to extend the life of the vessels to beyond 32 EFPY.

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TABLE 1 ZION 1 l Withdrawal I Capsule l Schedule l Fluence Designation i .(EFPY) I n/cm2 E71MeV l

-l _

I I T l Removed 1.16A l 2.9 x 1018 I I

~U l Removed 3.52A I 8.9 x 10188 I .

I X l ' Removed 5.17A l 1.4 x 1019 1 I YD l 8.5 l 1.8 x 1019C l- I W,S,V,Z l Standby 1 i l I I ZION 2 i Withdrawal l Capsule I -Schedule i Fluence Designation I (EFPY) I n/cm2 E71MeV

.l. .

l l l U l Removed 1.27A - l 3.6 x 1018 I I T I Removed 3.56A l 9.8 x 1018B I I YD l 8.5 l 1.8 x 1019C l l X l Standby i I I i W,S,V,Z l Standby l l l I I A Removed in accordance with Amendment Nos. 62 and 59~

'B . Corresponds to the approximate EOL fluence at the reactor vessel 1/4 T location.

C Corresponds to the approximate EOL fluence at the reactor vessel inner wall location.

D Contains weld metal WOL specimen i

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ATTACHMENT 3 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION PROPOSED CHANGES TO ZION TECHNICAL SPECIFICATIONS APPENDIX A - SECTION 4.3.4.D MATERIALS IRRADIDATION SURVEILLANCE SPECIMEN INSPECTION DESCRIPTION OF AMENDMENT REQUEST An amendment to the Zion Facility Operating License is proposed to revise the specimen capsule withdrawal schedule to reflect both the implementation of Low Leakage Loading Patterns and the current requirements of 10 CFR 50, Appendix H.

BACKGROUND 10 CFR 50.92 states that a proposed amenoment will involve a no significant hazards consideration if the proposed amendment does not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.

1 In adoition, the Commission has provided guidance in the practical l

application of these criteria by publishing eight examples in 48 FR 14870.

The discussion below below addresses each of these three criteria and demonstrates that the proposed amendment involves a no significant hazards consideration.

BASIS FDR NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Does the proposed amendment (1) Involve a significant increase in the probability ~ or consequences of an accident previously evaluated; or

(2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or

-(3) Involve a significant reduction in a margin of safety?

DISCUSSION - ITEM 1 This change only affects the withdrawal schedule for the specimen capsules installed inside of Zion's reactor vessels. This schedule is not a factor in any of the previously analyzed accidents. Thus, the change does not alter the probability or consequences of any accident previously evaluated.

DISCUSSION - ITEM 2 As discussed above, this change only addresses the timing of capsule withdrawal. The withdrawal of specimen capsules was considered in Zion's design and has previously taken place on numerous occasions. Thus, this change does not create the possibility for a new or different kind of accident.

DISCUSSION - ITEM 3 While Zion's margin of safety is insensitive to changes in capsule withdrawal schedules, this change will allow for a more meaningful reactor vessel surveillance program. Thus, the future properties of Zion's vessels can be more accurately predicted, providing a slight increase in the margin of safety.

Note that this change will bring Zion Station into compliance with the 1983 revision to 10 CFR 50, Appendix H. Thus, example vil is applicable in this situation. Example vil reads as follows:

(vil) A change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keeping with the regulations.

Therefore, since the application for amendment satisfies the criteria specified in 10 CFR 50.92 and is similar to examples for which no significant hazards consideration exists, Commonwealth Edison Company has made a determina-tion that the application' involves no significant hazards consideration.

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