ML20129A015
| ML20129A015 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Turkey Point |
| Issue date: | 10/03/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127A737 | List:
|
| References | |
| FOIA-84-794, REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8506040439 | |
| Download: ML20129A015 (9) | |
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c 7590-01 UNITED STATES NUCi. EAR REGULATORY COMMISSION FLORIDA POWER AND LIGHT COMPANY DOCKET N05. 50-250 AND 50-251 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT FACILITY OPERATING LICENSES AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating Licenses Nos. DPR-31 and DPR-41, issued to Florida Power and Light. Company (the licensee), for operation of the Turkey Point Plant Unit Nos. 3 and 4 located in Dade County, Florida.
These amendments would change the Technical Specifications to support the integrated program for vessel flux reduction to resolve the pressurized thermal shock issue and to take credit for operation with the new steam generators in_an unplugged (maximum of five (5) percent tube plugging) configuration.
Changes are requested to: (1) increase the hot channel F limit from I.55 AH to 1.62; (2) increase the total peaking factor F limit from 2.30 to 2.32; g
(3) change the overpower A T setpoints and thermal-hydraulic limit curves; and (4) delete restrictions and limits placed on the old steam generators to allow for operation with tubes plugged in excess of five (5) percent in i
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B506040439 841108 PDR FOIA ADATD84-794 PDR r
d 7590-01 -
in accordance with the licensee's application for amendments dated August-19
-1983 as supplemented September 9, 1983.
Before issuance of the proposed license amendments, the Commission will
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have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The Commission has made a proposed determination that the amendments request. involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments would 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.
The Commission has provided guidance concerning the application of the standards for determining whether license amendments involve no significant hazards considerations by providing certain examples (48 FR 14870).
The limit increase in the hot channel F limit and the total peaking factor Fq gg
4 7590-01 is similar to example (vi) of changes which are not likely to involve signi-ficant hazards considerations: A change which either may result in some increase to the probability or consequences of a previously analyzed accident or reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or compo-nent specified in the Standard Review Plan: for example, a change resulting from the application of.a small refinement of a previously used calculational
-model or design method.
The-reduction in the safety margin resulting from the increase in the F
and F limits are addressed in. the safety evaluation provided with the AH 4
submittal and indicate: (1) the calculated peak clad temperature of 1605 F and 1972*F for srall and large break loss of coolant accidents respectively, are within the maximum limit of 2200 F specified in 10 CFR 50.46, " Acceptance Criteria for Emergency Core Cooling Systems (ECCS) for Light Water Nuclear Power Reactors"; (2) additional. departure from nucleate boiling ratio margin is identified for Overtemp 4T and loss of flow conditions to accommodate the reduction in margin resulting from increasing the F loss of limit and is 4g within the Final Safety Analysis Report (FSAR) design basis; (3) for breaks up to and. including the double-ended severance of a reactor coolant pipe the ECCS will meet the acceptance criteria of 10 CFR 50.46; and (4) the overpower aT setpoints will be more restrictive to provide protection using the recalculated core limits and error allowances provideo in the safety evaluation which indicate the safety margin is within the acceptance criteria of the Standard Review Plan.
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, The change in the Overpower 4T setpoints and thermo-hydraulic limit curves are similar to example (ii) of changes not likely to involve significant hazards considerations: A change that constitutes an additional limitation or control. not presently included in the technical specifications:
for example, a more stringent surveillance requirement.
The changes requested in the setpoint
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and thermal-hydraulic limit curves are all in the conservative direction and constitute a more stringent limitation.
The deletion of the technical specifications relating to the old steam generators is similar to example (v) of changes not likely to involve signifi-cant hazards considerations:
Upon satisfactory ' ompletion of construction in c
connection with an operating facility, a relief granted from an operating restriction that was imposed because the construction was not yet completed satisfactorily.
This is intended to involve only restrictions where it is justified. that construction has been completed satisfactorily.
The deletions requested are to remove the restrictions placed on the use of the old steam generators with tubes plugged in excess of five (5) percent.
License conditions were placed on the Turkey Point Plant, Units 3 and 4, which requires a new ECCS.
analysis be performed if credit is to be taken for the unplugged configuration (maximum of five (5) percent tube plugging) for the new steam generators upon satisfactory completion of the construction associated with replacement of the steam generators. Construction has been satisfactorily completed and the licensee's s;bmittal includes new ECCS analysis which assumes a maximum tube
s 7590-01
. p ugging of five (5) percent. The results of the new analysis indicate that for breaks up to and including the double-ended severance of a reactor coolant pipe, the ECCS can perform its function and is within the acceptance criteria of 10 CFR 50.46 which demonstrates that the restrictions placed on the old steam generators are no longer applicable and the new steam generators function satisfactorily.
The Commission is seeking public comments on this proposed determina-tion. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
The Commission will not normally make a final determination unless it receives a request for a hearing.
Comments should be addressed to the Secretary of the Commission, U. S.
Nuclear Regulatory Commission, Washington, D. C.
20555. Attn:
Docketing and Service Branch.
By NOV 11 1983
, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene.
Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's
" Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by
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.i 7590-01 the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chainnan of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As re, quired by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceed-ing, and how that interest may be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of.the petitioner's property, financial, or other interest in -the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest.
The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the
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Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended cetition must satisfy the specificity requirements described above.
Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set
7590-01
. forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendments under consideration. A petitioner who fails to file such a supplement which satisfies those requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the older granting leave'to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
If a hearing is requested, the Commission will make a final determina-tion on the issue of no significant hazards consideration.
The final determination will serve to decide when the hearing is held.
If the final determination is that the amendments request involves no significant hazards consideration, the Commission may issue the amendments and'make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendments.
If the final determination is that the amendments involves a significant hazards consideration any hearing held would take place before the issuance of any amendments.
Normally, the Commission will not issue the amendments until the expira-tion of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendments before the expiration of the 30-day notice period,
7590-01
. provided that its final determination is that the amendments involves no The final determination will consider significant hazards consideration.
all public and State comments received. Should the Commission take this action, it wil publish a notice of issuance and provide for opportunity for The Commission expects that the need to take a hearing after issuance.
this action will occur very infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the' Commission, U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, 1717 H Street N.W., Washington, D. C., by the above date. Where petitions are filed.during the last ten (10) days of the notice period, it is requested that the petitioner promptly so inform the Commiss' ion by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identifica-tion Number 3737 and the following message addressed to Steven A. Varga, Chief, Operating Reactors Branch No. 1, Division nf Licensing: petitioner's name and telephone number; date petition was mailed; plant name; and publi-cation date and page number of this FEDERAL REGISTER notice.
A copy of the petition should also be sent to the Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to liarold F. Reis.
Esquire, Lowenstein, Newman, Reis and Axelrad, 1025 Connecticut Avenue, N.W., Washington, D.C.
20036.
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7590-01 Nontimely filings of petitions for leave to intervene, amended petitions.,
supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Comission, the presiding officer of the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request.
That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendments which is available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W... Washington,'D.C., and at the Environmental and Urbana Affairs Library, Florida International University, Miami, Florida 33199.
Dated at Bethesda, Maryland, this 3rd day of October 1983.
FOR THE NUCLEAR REGULATORY COMMISSION 1
Operating Reactor Branch #1 Division of' Licensing
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- 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION C0tWONWEALTH EDISON COMPANY DOCKET NOS. 50-295 AND 50-304 NOTICE OF CONSIDERATION OF ISSUANCE OF AMEN 0MENTS TO FACILITIES OPERATING LICENSES AND OPPORTUNITY FOR PRIOR HEARING The United States Nuclear Regulatory Comission (the Comission) is.
considering issuance of amendments to Facilities Operating License.Nos.
DPR-39 and DPR-48, issued to Commonwealth Edison Company (the licensee), for operation of the Zion Nuclear. Power Station, Unit,Nos. I and 2 located in Zion, Illinois.
The amendment would revise the provisions in the Technical Specifications to permit operation of the Unit Nos. I and 2 with only three of'the four coolant loops, when needed, in accordance with the licensee's application for
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amendments dated January 27, 1977..
Prior to issuance of th& proposed license amendments, the Commission will have made findings required by'the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
By October 31, 1983, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating licenses and any person whose Interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for -
leave te intervene. Request for a hearing and petitions for leave to intervene
.shall be filed in accordance with the Comission's " Rules of Practice for 4
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2, a Domestic Licensing Proceedings" in.10 CFR Part 2.
If a request for hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request'and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by-10 CFR 52.714, a petition 'for leave to intervene shall setforthwithparticularityftheinterestofthepetitionerintheproceedng, The and how that interest may be affected by the results of the proceeding.
petition should specifically explain the reasons why intervention-should be (1) the nature permitted with particular reference to the following factors:
of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other 6
interest in the proceeding; and (3) the possible effect of any order which may
'The petition should be entered in the proceeding on the petitioner's interest.
also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fif teen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file.a supplement to the petition to intervene which must include a list of the contentions which are sought to be
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7590-01
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litigated in the' matter, and the. bases for each contention set forth with reasonable. specificity. Contentions shall be limited to matters within the scope of the amendments under consideration.. A petitioner who fails' to file such a supplement which satisfied these requirements with respect to at least one contentio) will not be permitted to participate as a party. ;
Those permitted to intervene become parties to the proceeding, subject to any limitaticns in the order granting leave to' intervene, and have the oppor-tunity to participate fully in the conduct of the hearing, including the opportunity to present evidehc'e and cross-examine ' witnesses.
A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Comission, United States Nuclear Regulatory Comission, Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be
. delivered to the C~ omission's Public Document Room,1717 H Street, N.W., Washington, s
D.C. by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner or representative for the petitioner promptly so inform the Comission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following L
message addressed to Steven A. Varga, Chief, Operating Reactors Branch No. 1, Division of Licensing: petitioner's name and telephone number; date petition was mailed; plant namh; and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should.also be sent to the Executive 1
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7590-01
,er 4-Legal Director, U. S. Nuclear Regulatory Commission. Washington, D.C.
- 20555, and to P. Steptoe Esquire, Isham, Lincoln and Beale, Attorneys at law, Three First National Plaza, Sist Floor, Chicago, Illinois 60602, attorney for the licensee.
Nontimely filings of petitions' for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a detemination by the Connission, the presiding officer or the Atomic Safety and Licensing Board 6,esignated to rule en the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request.
That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendments dated Janaury 27, 1977, which is available for public inspection at the Conunission's Public Document Room,1717 H Street,'N.W., Washington, l
D.C. and at the Zion-Benton Public Library District, 2600 Enunaus Avenue, Zion. Illinois 60099.
l Dated at Bethesda, Maryland this 23rd day of September 1983.
FOR THE NUCLEAR REGULATORY CONMISSION i
o) fevenA.Varga,Cief Operating Reactors ranch No. 1 i
I Division of Licensing
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMIS5 ION COMMONWEALTH EDISON COMPANY DOCKET NOS. 50-295 and 50-304
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NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR PRIOR HEARING The United States Nuclear Regulatory Comission (the Comission) is considering issuance of an amendment to Facility Operating License No. OPR-39 and DPR-48 issued to Comonwealth Edison Company (the licensee), for operation of the Zion Nuclear Power Station, Unit 1 and 2 located in Zion, Illinois.
In accordan.ge with the licensee's application for amendmen't dated October 14, 1983 the amendment would permit temporary one-time changes to Zion Technical Spec-ifications regarding the Auxiliary Electric Power that would allow performing extensive preventive maintenance on the diesel generator shared between the two units.
Because that diesel generator is shared, extended maintenance periods have not have been available under present tecnnical specifications, even during scheduled refueling outages of either of the two units.
The proposed one-time changes would extend the present seven-day period to forty five days during which, with one unit in cold shutdown, only two diesel generators woulo oe required to satisfy the standby AC on-site power requirements.
Prior to issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
By February 13, 1984 the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to pa' ticipate as a party in the proceeding must file a written petition for leave r
NW-p m 14199
7590-01 1
to intervene.
Request for a hearing and petitions for' leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
If a request for hearing or petition for leave to intervene is filed by the above d' te, the Commission or an Atomic a
Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Sa fety and Licensing Board will issue.a notice of hearing or an appropriate order.
As required by 10 CFR 12.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding.
.The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest.
The petition should also identify the specific aspects (s) of the subject matter of the proceeding as to which petitioner wishes to intervene.
Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an-amended petition
'must satisfy the specificity requirements described above.
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Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of contentions which are sought to be litigated in the matter, and the bases for each contention set' forth with reasonable specificity.
Contentions shall be limited to matters within the scope of the amendment under consideration.
A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party Those permitted to intervene become parties to the proceeding, subject to any limitations in the ord,er granting leave to intervene, and have the oppor-tunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Conimission, United States t{uclear Regulatory Commission, Washington, D.C.
20555, Attention:
Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H Street, N.W.,
Washington, D.C. by the above date.
Where petitions are filed during the last :en (10) days at the notice period, it is reauestec that the petitioner or rearman at-for the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Steven A. Varga, Chief, Operating Reactors Branch No.1 Division of 1.icensing:
petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDER.
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7590-01 REGISTER notice.
A copy of the petition should also be sent to the Executive Legal Director, U. S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, and to P. Steptoe, Esquire, Isham, Lincoln and Beale, Attorneys at Law, Three First National Plaza, 51st Floor, Chicago, Illinois 60602, attorney for the licensee.
-Nontimely filings of petitions for leave to~ intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a detemination by the Commission, the presiding officer of the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request.
That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated October 14, 1983, which is available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C.
and at the Zion-Benton Public Library District, 2600 Emmaus Avenue, Zion, Illinois 60099.
Dated at Bethesda,. Mary. land this January 5,1984 F0p E NUCLEAR REGULATORY COMMISSION n
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l St ven A. Varga,)Chie s'
Operating Reactors Bratcp No.1 c
Division of Licensing
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7590-01 U. S. NUCLEAR REGULATORY COMMISSION CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 NOTICE OF CONSIDERATION OF ISSUANCE OF AMEN 0 MENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Comission (the Commission) is considering issuance of amendment to Facility Operating License No. OPR-23, issued to Carolina Power and Light Company (the licensee), for operation of the H. B. Robinson Steam Electric Plant Unit No. 2 located in Darlington County, South Carolina.
The amendment:
A.
Involves a core reload and would permit operation with Exxon Fuel Assemblies with up to 3.9 weight percent U-235 and to extended burnups of 44,000 MWD /MTU maximum assembly average exposure in addition to Exxon Fuel during Cycle 9.
Part length Shielded Assemblies (PLSA) containing 1.24 weight percent U-235 are included in the core periphery (the " flats") as part of the pressurized thermal shock program to reduce the fast neutron fluence to the pressure vessel walls.
The PSLA are mechanically identical to the reload XN-7 assemblies except that the bottom 42" of the fuel column is replaced with stainless steel rod for neutron shielding.
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. Numerical changes to the Technical Specifications are
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required due to the (1) addition of the PSLA and (2) utilizing a low leakage core.
Specifically, hot channel factors (F and F4 H) limits and the beginning of cycle (B0C) g moderator temperature coefficient are being increased.
The overtemperature and overpower A T setpoints will be reduced as a result of increasing F and F limits.
There is no g
AH request to increase the authorized power of the facility.
The changes, discussed above, are required to account for adding the PSLA in the core periphery (" flats") and due to improved fuel utilization resulting from a low leakage core.
B.
Would modify the Technical Specification to add a requirement for the number of reactor coolant pumps operating at less than 2%
reactor power. The revised specification would provide flexibility and cooldown of the plant by allowing operation, with less than two pumps, under one of three conditions which precludes the potential for the uncontrolled rod withdrawal transient.
This change is required due to inconsistencies found between the FSAR analyzed uncontrolled rod withdrawal transient at low power or subcritical conditions and the Technical Specification'and to assure that the transients are bounding in the respective categories.
C.
Would modify the Technical Specification to achieve consistency within the Technical Specifications and with current operating practices such as deleting references to N-1 loop operations, references to reduce T,yg programs, and references to the original FSAR, which is being updated annually.
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est These revisions to the technical specifications would be made in response to the licensee's application for amendment dated July 23 1984.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as ' mended (the Act), and the Comission's regulations.
The Comission has made a proposed detennination that the amendment request involves no significant hazards consideration.
Under the Comission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would 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.
The Comission has provided guidance concerning the application of these standards by providing certain examples (48 FR 14870).
Examples of actions likely to involve no significant hazards considerations are:
(1) purely administratiave change to technical specifications:
for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature.
(ii)
A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications:
for example, a more stringent surveillance requirement.
(iii)
For a nuclear power reactor, a change resulting from a nuclear reactor core reloading, if no fuel assemblies significantly different from those found previously acceptable to the NRC for a
7590-01,
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 NRC has previously found such methods acceptable.
QangeA-Reload Although axially blanketed fuel and the part length shielded assemblies are significantly different from those previously found acceptable for previous cores, they are significantly more conservative.
They produce much less power, therefore, fewer neutrons and lower temperature. Analyses submitted have supported a no signficant hazards considerations.
Analyses have been performed and the results submitted to the Commission justify increasing the F and F as well as an increase in the q
AH BOC moderator temperature coefficient below full power.
A reanalysis of the boundi,ng Chapter 15 analyses has been performed which req'uire changes to overtemperature and overpower 4 T setpoints.
ENC's new XNB and DNB correlations were utilized in perfonning the reanalyses of the Chapter 15 events.
The results of these analyses show that the changes are clearly within acceptable criteria.
To preclude the continuous use of APDMS for Cycle 10 and future cores an improved approach (procedure) will be used.
These procedures, " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors, Phase II, or PDC-II have been generically approved.
A safety analyses has.been performed for this methodology to support the change in methodology for H. B. Robinson.
The results show the change to be clearly within all acceptable critieria.
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J 7590-01 Based on the above review, the core reload application is similiar to example (iii) above, therefore, the staff proposes a no significant hazards consideration.
Change B This change placed additional restrictions in the Technical Specifications regarding RC and RHR pump operability for various core conditions to assure that the uncontrolled rod withdrawal transient at low power or subscritical conditions are bounding in their respec'tive categories.
This change is similar to example (ii) above.
On this basis, the staff proposes a no significant hazards consideration.
Change C This change to the Technical Specifications deletes out-of-date references that no longer apply, therefore, they are administrative in nature and provide consistency within the specifications and between the specifications and between the specifications in other documents.
This change matches example (i) above.
Therefore, the staff proposes a no significant hazards consideration.
The Commission is seeking public comments on this proposed determination of no significant hazards consideration.
Therefore, based on these considerations and the three criteria given above, the Comission has made a proposed determination that the amendment request invovies no significant hazards consideration.
The Commission lias determined that failure to act in a timely way would result in extending the licensee's shutdown for steam generator repair and core reload.
The licensee's startup is several months ahead of schedule.
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~ Therefore, the Comission has insufficient time to issue its usual 30-day notice of the proposed action for, public coment.
If the proposed determination becomes final, an opportunity for a hearing will~ be published in the Fedear Register at a later date and any hearing request will not delay the effective date of the amendment.
If the Comission decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register' and, if a hearing is granted, it will be held before any amendment is issued.
The Comission is seeking public comments on this proposed determination of no significant hazards consideration.
Comments on the proposed determination may be telephoned to Steven A. Varga, Chief of Operating Reactors Branch No. 1, by collect call to 301-492-8035 or submitted in writing to the Secretary of the Comission, U. S. Nuclear Regulatory Comission, Washington, D.C. 20555, Attn: Docketing and Service Branch. All coments ceceived by September 14, 1984 will be considered in reaching a final determination.
A copy of the application may be examined at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Hartsville Memorial Library, Home'and Fifth Avenues, Hartsville, South Carolina 29535.
Dated at Bethesda, Maryland, this August 17, 1984 FOR THE NUCLEAR REGULATORY COMMISSION I
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