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#REDIRECT [[U-601239, Application for Amend to License NPF-62,revising Tech Spec to Support Cycle 2 in Max Extended Operating Domain & W/ Reduced Feedwater Temps.Supporting Documentation Encl.Fee paid.NEDC-31546P Withheld]]
| number = ML20154A199
| issue date = 09/06/1988
| title = Application for Amend to License NPF-62,revising Tech Spec to Support Cycle 2 in Max Extended Operating Domain & W/ Reduced Feedwater Temps.Supporting Documentation Encl.Fee paid.NEDC-31546P Withheld
| author name = Hall D
| author affiliation = ILLINOIS POWER CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000461
| license number =
| contact person =
| document report number = A00L-880906, AL-880906, U-601239, NUDOCS 8809120107
| package number = ML19297G893
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 9
| project =
| stage = Request
}}
 
=Text=
{{#Wiki_filter:_ ____ __-.      - __                __    ____ -
        ;/ ' -                                                                U-601239 f                                                                      L47-88( 09 46 )-LP
        /-                                                                      8E.110 e                ILLIN0/8 POWER 00MPANY                                                            i
;                                                                  10CFR50.90 DPH-0798-88
  ,                        Docket No. 50-461                      september 6, 1988 4
Document Control Desk Nuclear Regulatory Commission Washington, D.C.          20555                                              ,
 
==Subject:==
Clinton Power Station Proposed Amendment to                    i Facility Operating License NPF-62
 
==Dear Sir:==
Pursuant to 10CFR50.90, Illinois Power Company (IP) hereby applies for an amendment of Facility Operating License NPF-62 Clinton Power Station (CPS). Changes to the CPS Technical Specifications are being requested to support the first refueling of the CPS reactor with new fuel types                  -
and to support subsequent reactor operation (Cycle 2) in the                l Maximum Extended Operating Domain (&70D) and with reduced feedwater temperatures.* To support these requests the following attachments are included:
Attachment 1 - Affidavit Attachment 2 - Description of Proposed Technical Specification Changes Related to the Reload and                i MEOD Analyses (including mark-ups of the affected Technical Specifications)
At- chment 3 - Technical Specification Changes                  l Required to Support Refueling                                  i
* Attachment 4 - Technical Specification Changes Re uired to Support Operation Consistent with the
                                          "! IMUM EXTENDED OPERATIN) DOMAIN AND FEEDWATER                i HEATER OUT-OF-SERVICE ANALYSIS FOR CLINTON POWER              l STATION" (MEOD/FWHOS)*
* An analysis which justifies reactor operation with reduced feedwater temperature as low as 370*F at rated conditions (included in Attachment 4) was performed in accordance with the provisions of Section 15.1 of Supplement No. 7 to the Clinton Safety Evaluation Report.
Amproval of this proposed license amendment containing the analysis for reduced feedwater temperature will require revision or deletion of License Condition 2.C.(10) in the Clinton Power Station Operating License asthelicensoconditionwasrequiredinaccordancewith[f9Pj Section 15.1 of SSER 7 eso91201o7 eso906                                    s/t p DR    ADOCK0500gg61
                                                                                            $f/3V467
 
U-601239 L4 7-88 (09 - 06 ) -LP 8E.110                ,
Attachment 5 - Basis for No Significant Hazards Consideration (for the Technical Specification Changes Proposed as a Result of Operation with New Fuel Types and in the MEOD Region)
Attachment 6    "SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR CLINTON POWER STATION UNIT 1, RELOAD 1, CYCLE 2, 23A5921 Rev. 0" Attachment 7    "MAXIMUM EXTENDED OPERATING DOMAIN AND FEEDWATER HEATER OUT-OF-SERVICE ANALYSIS FOR CLINTON POWER STATION, NEDC-31546P, August 1988"*
Attachment 8 - Proposed Startup Test Plan for Cycle 2 This proposed amendment also requests revision to Technien1 Specification Table 3.3.7.4-2, REMOTE SHUTDOWN SYSTEM CONTROLS, to include additional control switches for valves lE12-F068B and lE12-F014B and circuit breaker 252-ATlAA1. This change provides for controls to enhance the operation of the subject components to comply with the NRC Staffs' guidance for implementing 10CFR50, Appendix A, Criterion 19 (GDC 19) as referenced in paragraph 7.4.3.1 of the Clinton Power Station Safety Evaluation Report (SSER NO.
6). The Description, Justification and Basis for No Significant Hazards Consideration for this change are contained in Attachment 9.
Additionally a change to Technical Specification 4.4.1.2 is requested. This change will clarify the jet pump surveillance requirements of this specification and incorporate the guidance provided in General Electric Service Information Letter No. 330.      The Description, Justification and Basis for No Significant Hazards Consideration for this proposed changa are contained in Attachment 10.
In accordance with the provisions of 10CFR170.12 and 170.21, IP is enclosing a check made out to the U.S. Nuclear Regulatory Commission in the amount of $150.00 as payment of the application fee for this amendment.      In addition, pursuant to 10CFR50.91(b)(1), a copy of this request for amendment has been sent to the Illinois Department of Nuclear Safety.
* Attachment 7 is proprietary and was provided to IP from Genercl Electric under the terms of an agreement which forbids disclosura to others except as allowed for disclosure to a governmental authority to the extent necessary to secure governmental authorizations.
 
U-601239 L47-88(0? 06 )-LP 8E.110 IP has reviewed the proposed Technical Specification changes against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a              >
significant hazards consideration, do not significantly            i increase the amounts or change the types of effluents that may be released offsite, nor do they significantly increase individual or cumulative occupational radiation exposures.
Based on the foregoing, IP concludes that the proposed Technical Specification changes meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement,                i It is IP's intent to implement the proposed changes for Cycle 2 commencing with the startup from the first refueling      i outage. Therefore, to supaort Cycle 2 startu      NRC review    i and approval is requested by January 3, 1989,p,he  t  scheduled    !
start date for the outage.
S    rel  yours, D. P. Hall Vice President                    i l
GSL/cke                                                            j Attachments cc:  NRC Resident Office NRC Region III, Regional Administrator NRC Clinton Licensing Project Manager                        y Illinois Department of Nuclear Safety l
L l
l l
I I
i I
i
 
Attechm:nt 1
-                                                                to U-601239 STATE OF ILLINOIS COUNTY OF DEWITT DONALD P. HALL, being first duly sworn, deposes and says:      That he is Vice President of Illinois Power Company:
that the provided information has been prepared under his supervision and directions that he knows the contents thereofi and that to the best of his knowledge and belief said request and the facts contained therein are true and correct.
DATED:      This      day of September 1988
                                                /
Signed:                    /
Donald F. Hall Subscribed and sworn to before me this & day of September 1988.
1- _ _ _*0fflCIAL CEAL" Nctay u e, Sta e cf UnsA            W-          '#
            ' I4 Comss;:n Eyrn 10/1/93                Notary Public
              .:_=____ - _ - _ __--'l
 
9
  .-                                                                                                                                                                                    Attcchucnt 2 to U-601239 page 1 of 58 Description of Proposed Technical Specification Changes Related to the Reload and MEOD Analyses Technical        Technical Spacification    Specification                                                                                                                                                            Reason for Page No.          Section                                        Description of Change                                                                                                  Change 1,111, iv, v. Index                    The index is being revised to                                                                                                                  Consistency xv i *
* accurately reflect the insartions, deletions, and renumbering caused by the changes listed below.
1-2              1.9                      Replace "the General Electric                                                                                                              Clarification
* Critical Quality Boiling Length (GEXL)" (correlation) with "an approved GE Critical Power" (correlation) in the definition of Critical Power Ratio.
1-3              1.15                      Delete this Specification.                                                                                                                        MEOD 1-3              1.16                      Delete this Specification.                                                                                                                        MEOD 1-4              1.23                      Delete this Specification.                                                                                                                        MEOD 2-1              2.1.2                    Change the MCPR Safety Limit for two                                                                                                            Reload recirculation loop operation from 1.06 to 1.07 and change the MCPR Safety Limit for single recirculation loop operation from 1.07 to 1.08.                                                                                                                                I 2-3              Table 2.2.1-1            Revise the trip setpoint for APRM Flow                                                                                                            MEOD Biased Simulated Thermal Power-High trip channels during two recirculation loop operation. The trip setpoint for single recirculation loop operation will be listed separately, but will retain its current value.
B2-1              B2.1.0                  Replace specific values for the MCPP.                                                                                                      Clarification
* Safety Limit with a reference to Technical Specification 2.1.2.
B2-1              B2.1.1                    Replace "GEXL Correlation" with                                                                                                            Clarification *
                                                  "an approved CE critical power correlation (Reference 1)".
o To support future reloads cc Index pages may be revised as necessary to include appropriate information
 
  .                                                                                                  Attechment 2 to U-601239 page 2 of 58 Technical      Technical Sp:cification    Specification                                              Reason for Page No.        Section            Description of Change                Change, B2-2            B2.1.2        Remove the specific description of        Clarification
* analysis methods used to determine the MCPR Safety Limit and replace it with a reference to the "General Electric Standard Application for Reactor Fuel (CESTAR)"
NEDE-24011-P-A-8.
32-3            Table B2.1.2-1 Delete table - information is            Clarification
* contained in the "General Electric Standard Application for Reactor Fuel (CESTAR)" NEDE-24011-P-A-8.
B2-4            Table B.I.2-2  Delete table - information is            c'.arification*
contained in the "General Electr.
Standard Applicatioa for Reactor .e l (GESTAR)" NEDE-24011-P-A-8.
B2s7            B2.2.1        Remove the reference to Technical              MEOD Specification 3.2.2.
3/4 1-6          3.1.3.2        Delete the footnote granting relief        Clarification from scram time testing during the initial fuel cycle.
3/4 1-8          4.1.3.2        Delete the footnote granting relief        Clarification from scram time testing during the initial fuel cycle.
3/4 2-1          3/4.2.1        Change to reference the appropriate        Clarification figures.
Add reference to the MAPFAC and MAPFACI        MEOD as figures 3.2.1-1 and 3.2.f-2 respectively.
Add a reference to each of the new            Reload MAPLHGR Figures 3.2.1-6 and 3.2.1-7 for each of the new fuel types.
3/4 2-2          Fig. 3.2.1-1  Add a new figure with MAPFAC cu rve .          MEOD f
3/4 2-3          Fig. 3.2.1-2  Add a new figure with MAPFAC cu rve .          MEOD 3/4 2-4          F1.g. 3.2.1-3  Revise figure and page nutber only.          Consistency 3/4 2-4A        Fig. 3.2.1-4  Revise figure and page number only.          Consistency
                              # To support future reloads i
4
 
      ,                                                                                                                                Attcchment 2 to U-601239 page 3 of 58      i t
Technical                                    Technical Spacification                                  Specification                                                . Reason for  i Page No.                                      Section              Description of Change                  Change 3/4 2-4B                                        Fig. 3.2.1-5    Revise figure and page number only.          Consistency 3/4 2-4C                                        Fig. 3.2.1-6    Add a new MAPLHGR Curve for a new fuel          Reload type.
3/4 2-4D                                        Fig. 1.2.1-7    Add a new MAPLHGR Curve for a new fuel        Reload    i type, i
3/4 2-5 &                                      3/4.2.2          Delete the entire Specification;                MEOD    t 3/4 2-6                                                          retain the page and leave it intentionally blank.                                      ,
I 3/4 2-8                                        Fig. 3.2.3-1    Replace existing MCPR and MCPRp curves          MEOD    !
^
3/4 2-9                                        Fig. 3.2.3-2    with curves that incobporate MEOD and                    [
Reduced Feedwater Temperature Analyses.                  [
I Table 4.3.1.1-1  Remove the reference to Technical 3/4 3-10                                                                                                          MEOD Specification 3.2.2.
f 3/4 3-66                                        Table 3.3.6-2    Revise APRM Flow Biased Neutron Flux                      >
Upscale Rod Block for two recirculation loop operation. The                        ,
APRM Flow Biased Neutron Flux Upscala                    !
Rod Block for single recirculation                        j loop operation will be listed                    MEOD separately, but will retain its                            ,
current value.                                            t Revise Reactor Coolant System                    MEOD    ,
Recirculation Flow - Upscale Trip Setpoint and Allowable Value to allow for operation in the MEOD.
3/4 3-67                                        Table 3.3.6-2    Remove reference to Technical                    MEOD      i Specification 3.2.2.                                      [
l 3/4 3-91                                        3.3.7.7          Remove requirement to monitor MFLPD.            MEOD      j 3/4 4-1                                        3.4.1.1.        Revise MCPR Safety Limit to 1.08.              RELOAD    f ACTION a.1 c.
3.4.1.1          Remove reference to reducing                    MEOD      l ACTION a.1.d    the MAPLHGR limit to a value of 0.85 times the two recirculation loop operation limit.                                      l t
3.4.1.1.        Remove reference to Technical                    MEOD      l ACTION a.1.e. Specification 3.2.2.                                      ;
i m,                          _ - . , . - - - , , - _ , .- -- ... , .,..,,_ _ _. - ,_, - - ,,          ._ -    _ _ . - _
 
          .                                                                                                                    Attcchment 2 to U-601239 page 4 of 58 Technical        Technical Sp:cification    Specification                                                                                                          Reason for Page No.          Section            Description of Change                                                                            Change B3/4 2-1          B3/4.2.1        Add a paragraph describing how the                                                                      MEOD B3/4 2-2                          MAPFAC curves are to be used and how they were determined.
Revise the section so that it refers                                                                Clarification to the correct MAPLHGR and MAPFAC curves.
Revise the last paragraph to discuss                                                                    MEOD the MAPLHGR requirements during single recirculation loop operation.
Add a discussion of how the "Runout                                                                      MEOD Flow" tolerances are determined.
B3/4 2-2          B3/4.2.2        Delete this section.                                                                                    MEOD B3/4 2-3          Table B3.2.1-1  Revise Fuel Types to include Reload                                                                      Reload Cores.
Revise *** note to add additional                                                                        MEOD information on assumptions used for initial MCPR.
B3/4 2-4          B3/4.2.3        Replace the specific MCPR Safety Limit                                                              Clarification
* with reference to Technical Specification 2.1,2.
Replace the reference to specific                                                                  Clarification
* analysis with reference to CESTAR.
Replace "105% of rated steam" with                                                                      MEOD "most limiting power".
Add a discussion of how the "Runout                                                                      MEOD Flow" tolerances are determined.
B3/4 2-5          B3/4.2.3        Add the discussion about MCPRp limits                                                                    MEOD when power is less than 40% of RATED THERMAL E0WER.
93/4 2-6          References      Replace the specific references with                                                                Clarification
* a reference to GESTAR, and add MEOD as a reference.
* To support future reloads
_ - _ .                  _            . . .                - _ _}}

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