ML20206E685
| ML20206E685 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/08/1987 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20206E663 | List: |
| References | |
| NUDOCS 8704130689 | |
| Download: ML20206E685 (5) | |
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ATTACHMENT 1 PROPOSED ZION APPENDIX A TECHNICAL SPECIFICATION CHANGES TO SECTION 4.3.4.D MATERIALS IRRADIATION SURVEILLANCE SPECIMEN INSPECTION Pages Modified:
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LIMlilNG COND1110N FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.4 4.3.4.0.
Materials Irradiation Surveillance Specimen-Inspection. (per unit)
Sr cimen capsules to be used in the reactor vessel material surveillance program shall be withdrawn during the refueling period either immediately preceding or following the Effective Full Power Years (EFPY) of unit life as follows: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-Z 32 W,S,V STANDBY UNIT 2 CAPSULE CAPSULE DESIGNATION REMOVAL TIME (EFPY)
U REMOVED (1.27)
T REMOVED (3.56)
Y 8.5 X
13 W,S,V,Z STANDBY 105 10670
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4.3.4 lhe surveillance inspection program has been developed to comply with Section XI.of. the ASME Boller and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, 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 evaluate the ef fects of radiation on the -
f racture toughness of reactor vessel steel based on the transition-temperature approach and 'the f racture mechanics approach.
10CFR50, 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-life fluences at I
the reactor vessel surface and 1/41 wall thicknesses. Previous capsules were removed under Amendment Hos. 62 and.59.
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ATTACMENT 2
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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 REOUEST An amendment to the. Zion Facility Operating License is proposed to revise the specimen capsule withdrawal schedule to incorporate the removal of two additional specimen capsules at fluences of excess of those expected at End of Lite. This is consistent with the requirements of 10 CFR 50, Appendix H.
BACKGROUND 10 CFR 50.92 states that a proposed amendment 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.
In addition, the Commission has provided guidance in the practical application of these criteria by publishing eight examples in 48 FR 14870.
The discussion below addresses each of these three criteria and demonstrates that the proposed amendstent involves a no significant hazards consideration.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDEFATION 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?
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, l 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 evsluated.
l 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, b
In addition, the withdrawal schedule has no effect on the performance of_any'of Zion's systems or structures.. Based upon this lack of system interaction, the proposed change will not affect any of the pre-existing
- accident sequences contained in Zion's PSAR.
Thus, this change does not create the possibility for a new or different kind of accident.
i DISCUSSION - ITEM 3 i
While Zion's margin of safety is insensitive to changes in capsule withdrawal schedules, this change will allow for a more meaningful reactor-l 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.
I Note that this change will bring Zion Station into compliance with the 1983 revision to 10 CPR 50, Appendix H.
Thus, example vii is applicable i
in this situation. Example vii reads as follows:
(vii)
A change to make a license conform to changes in the regulations, where the license change results in very minor-changes to facility
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operations clearly in keeping with the regulations, j-Therefore, since the application for amendment satisfies the criteria L
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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