ML20217H945
| ML20217H945 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/30/1998 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20217H931 | List: |
| References | |
| NUDOCS 9804060126 | |
| Download: ML20217H945 (32) | |
Text
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i ATTACIIMENT B !
License Amendment Request Number 98-05, Revised Section 6.0, Administrative Controls to reficct Defueled Status ZION NUCLEAR GENERATING STATION MARKEL) UP ANNOTATED COPY AND CLEAN COPY OF i TECIINICAL SPECIFICATIONS I FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECHNICAL SPECIFICATIONS ;
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ATTACHMENT B AFFECTED PAGES OF TIIE CTS ANNOTATED TO SilOW PROPOSED CIIANGES AND CLEAN COPY OF TIIE AFFECTED PAGES WITII PROPOSED CIIANGES INCORPORATED The following pages of the Zion Technical Specifications are affected by the proposed change:
Page Number Amendment 300 171 / 158 301 171 /158 309 143 / 132 310 171 /158 310b 171 /158 311 171 /158 325 146/134 326 146 /134 327 96/86 l
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Affected Pages of the CTS Annotated to Show Proposed Changes j
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ATTAC11 MENT C License Amendment Request Number 98-05, Revised Section 6.0, Administrative Controls to reficct Defueled Status ZION NUCLEAR GENERATING STATION EVALUATION OF SIGNIFICANT HAZARD CONSIDERATIONS FOR PROPOSED CIIANGES TO FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECilNICAL SPECIFICATIONS
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1 l ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION Comed has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated; Create the possibility of a new or different kind of accident from any previously analyzed; or Involve a significant reduction in a margin of safety.
The proposed amendment is being requested to facilitate plant activities following i the permanent shutdown and defueling of Units I and 2. The proposed amendment requests restoration of Custom Technical Specifications (CTS) which )
had been replaced with Improved Technical Specifications (ITS) by a previously issued but unimplemented Amendments (178/165). The proposed amendment i' would maintain CTS as the specifications governing activities at Zion Station. As part of the restoration of the CTS, the five License Conditions (2.C.(4),2.C.(7)(b),
2.C.(8),2.C.(9),and 2.C.(10)) which were deleted by Amendments 178/165 would be reinstated.
The proposed amendment would also change certain provisions of Section 6 of -
the CTS ," Administrative Controls." These changes would alter management titles and responsibilities, allow use of Certified Fuel Handlers in lieu of personnel licensed in accordance with 10 CFR 55, reduce the number of personnel required on shifl, change the required crew composition, and alter verbiage which implies that the units are still operational.
The determination that the criteria set forth in 10 CFR 50.92 are met for this amendment request is indicated below:
' Does the change involve a significant increase in the probability or consequences of an accident previously evaluated? ]
With a plant permanently shutdown and defueled the spectrum of accidents and events that remain credible is significantly reduced. As discussed below the proposed changes do not affect the probability or consequences of any accidents that do remain credible.
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l ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION The restoration of the CTS which were replaced with the ITS by Amendments 178/165 cannot increase the probability or consequences of any event or accident because the amendment was never implemented. The CTS have been maintained as the legally binding Technical Specifications in effect at Zion Station. The reinstatement of the five License Conditions deleted by Amendments 178/165 is an administrative change in that the requirements contained in the License Conditions had been relocated elsewhere and are now being restored exactly as they were before the amendment was issued. Since the actual requirements have not changed there can be no change in the probability or consequences of any accident or event.
The changes in management titles and responsibilities will not increase the probability or consequences of any accident or event because these changes are administrative and will not result in any decrease in the quality of management applied to Zion Station. The changes are commensurate with the significant reduction in site activities, site staffing, and risk to public health and safety that occurs when an operational nuclear power plant transitions to a permanently shutdown and defueled plant. Responsible individuals will have the authority to commit the personnel and resources necessary to fulfill their obligations for safe storage and handling of nuclear fuel. The change of position designations will have no effect on the frequency of occurrence of accident or event initiators, or on their consequences.
The changes to allow itse of Certified Fuel Handlers in lieu of personnel licensed in accordance with 10 CFR 55 will not increase the probability or consequences of an accident or event because the Certified Fuel Handler Training and Retraining program (which will be approved by the NRC) has been developed using a Systems Approach to Training as defined in 10 CFR 55.4. This approach provides nssurance that the Certified Fuel Handlers have the knowledge, skills, and abilities that are commensurate with the tasks to be performed (i.e., the proper monitoring, handling, storage, and cooling of nuclear fuel). Therefore the frequency of occurrence of accident or event initiators is not increased and the consequences of the accidents or events are unaffected, j i
The changes in shift staffing numbers and crew composition will not increase I l
the probability or consequences of an accident or event. These staffing changes are commensurate with the quantity, complexity, and hazard level of the activities required for storage and handling of nuclear fuel. The i
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i ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION elimination of the Shin Control Room Engineer does not affect any accident or event initiator or consequence since the previous specification would not have required that the position be manned with both units shut down. The elimination of the requirement for a Radiation Protection Person on shift will l have no effect on the frequency of occurrence of accidents or events, nor on the consequences of the accident or event.
l The changes in verbiage to eliminate any implication that units are operational j will not increase the probability or consequences of an accident or event because they are largely editorial changes and do not increase the frequency of j occurrence of or event initiators, nor do they increase the consequences.
l Therefore this proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The changes proposed by this amendment do not involve new structures, systems, or components, or the use of existing structures, systems, or components in a new manner. Consequently no new failure mechanisms are introduced. The design and operation of structures, systems, or components is unaffected by:
The restoration of CTS, The reinstatement of the five License Conditions deleted by Amendments 178/165, The changes in management titles and responsibilities, The changes to allow use of Certified Fuel llandlers in lieu of 10 CFR 55 licensed personnel, The changes in shift stafling numbers and crew composition, or The changes in verbiage to eliminate any implication that units are operational.
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.Therefore, the proposed changes do not create the possibility of a new or j i different kind of accident from any previously evaluated. I i )
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1 ATTACHMENT C l
l SIGNIFICANT HAZARDS CONSIDERATION Does the change involve a significant reduction in a margin of safety? 1 One of the License Conditions that would be reinstated by this amendment establishes limits that help ensure that the assumptions of the fuel bandling accident analysis remain valid. License Condition 2.C.(7).b limits the weight ofloads carried over fuel stored in the spent fuel pool to the weight of a single i fuel assembly plus the tool for moving that assembly. This weight limit ensures that the number of fuel rods broken in a fuel handling accident does )
not exceed the maximum number of fuel rods assumed to break in the accident !
analysis. Consequently, this change continues to provide assurance that the margin of safety involving the number of fuel rods broken in the accident will not be reduced.
i Therefore, these changes do not involve a significant reduction in the margin i ofsafety.
I Based upon the above evaluation, Comed has concluded that these changes involve no significant ha7ards consideration.
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I ATTACllMENT D License Amendment Request Number 98-05, Revised Section 6.0, Administrative Controls to reflect Defueled Status ZION NUCLEAR GENERATING STATION !
ENVIRONMENTAL ASSESSMENT STATEMENT i FOR PROPOSED CIIANGES TO l FACILITY OPERATING LICENSES i DPR-39 AND DPR-48 i APPENDIX A TECIINICAL SPECIFICATIONS I
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ATTACHMENT D l
ENVIRONMENTAL ASSESSMENT l
Comed has evaluated this proposed operating license amendment request against the criteria for identification oflicensing and regulatory actions requiring !
environmental assessment in accordance with 10 CFR 51.21. Comed has l determined that this proposed license amendment request meets the criteria for a l categorical exclusion set forth in 10 CFR 51.22(c)(9) and as such, has determined f
that no irreversible consequences exist in accordance with 10 CFR 50.92(b). This l determination is based on the fact that this change is being proposed as an 1 amendment to a license issued pursuant to 10 CFR 50 that changes a requirement l with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria l
(i) the amendment involves no significant hazards consideration.
As demonstrated in Attachment C, this proposed amendment does not involve any significant hazards consideration.
(ii) there is no significant change in the types or significant increase in the amounts of any effluent that may be released of fsite.
As documented in Attachment A, there will be no change in the types or significant increase in the amounts of any effluents released offsite.
(iii) there is no significant increase in individual or cumulative occupational j radiation exposure. i The proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of !
controls or methodology used for processing of radioactive effluents or !
handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant. Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
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f f ATTACHMENT E COMMITTMENTS i
i List of Commitments identified in ZRA980016 l
The following table identines those actions committed to by Comed in this document. Any otact actions discussed in this submittal represent intended or planned actions by Comed. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify Mr. Robert Godley, Zion Station Regulatory Assurance Manager, of any questions regarding this document or any associated regulatory commitments.
Commitment Committed Date A License Amendment Request concerning Permanently Defueled Third Quarter,1998 Technical Specincations will be proposed by Commonwealth Edison.
Radiation Protection coverage will be determined in accordance with the Prior to i
station's Radiation Protection and Emergency Preparedness programs. implementation of Station procedures will require that a Radiation Protection Person be on this proposed site during handling ofirradiated fuel. amendment.
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l-ATTACHMENT F REFERENCES 1
References:
- 1) Letter from O. D. Kingsley, Comed, to U. S. NRC, dated February 13,1998, Certification of Permanent Cessation of Operations i
- 2) Letter from O. D. Kingsley, Comed, to U. S. NRC, dated March 9,1998, Certification of Permanent Fuel Removal .
I
- 3) Letter from C. Y. Shiraki, U. S. NRC, to O. D. Kingsley, j '
Comed, dated December 19,1997, Issuance of Amendments 178/165 to Facility Operating Licenses DPR-39 and DPR-48, Improved Technical Specifications
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- 4) Letter from John C. Brons, Comed, to U. S. NRC, dated February 12,1998, concerning Commitment to comply with custom Technical Specifications and Deleted License
, Conditions
- 5) Letter from J. C. Brons, Comed, to U. S. NRC, dated March 16,1998, Request for Approval of Certified Fuel liandler Training and Retraining Program
- 6) Letter from J. II. Mueller, Comed, to U. S. NRC, dated January 21,1997, Application for Amendment to Facility Operating Licenses to Authorize use of the Entire Topical Report, CEN-629-P, for Installing Sleeves in Steam Generator Tubes i
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