View source for SVP-99-001, Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info

{{Adams
| number = ML20205J960
| issue date = 03/30/1999
| title = Application for Amends to Licenses DPR-29 & DPR-30,deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info
| author name = Dimmette J
| author affiliation = COMMONWEALTH EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000254, 05000265
| license number = 
| contact person = 
| document report number = SVP-99-001, SVP-99-1, NUDOCS 9904120277
| package number = ML20205J963
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 9
| project = 
| stage = Request
}}

=Text=
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  .&           Quad Cities Generating $tation 22?]O 2(bth penue North Cordova, II. 61212 9"' 60 m S m s u21i j
SVP-99-001 March 30,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D C 20555 Quad Cities Nuclear Power Station, Unit I and Unit 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

==Subject:==
Application for Amendment to Fncility Operating Licenses

==References:==
(a)      Unit 1 License Amendment 25 dated March 12,1976 (b)      Unit 2 License Amendment 12 dated April 21,1975 Pursuant to 10 CFR 50.90, Commonwealth Edison (Comed) Company proposes to                         '
amend Facility Operating Licenses DPR-29 and DPR-30. The proposed changes revise the Operating Licenses to delete various license conditions that have been completed,             )
make editorial changes and provide clarifying information. The proposed amendment                 {
requests changes to the following license conditions:                                             )
: 1) License Conditions 3.D for DPR-29 and DPR 30," Equalizer Valve Restriction,"
wording changes to be consistent with the design analysis and provide clarification          l of the operational configuration.                                                       t    j
               ' 2) License Conditions 3.M for DPR-29 and 3.L for DPR-30, " Surveillance Requirements," have been satisfied and are no longer required.
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: 3) License Conditions 3.N for DPR-29 and 3.M for DPR-30," Additional Conditions 9b f      I Appendix C," have been satisfied and are no longer required.
: 4) License Condition 3.A for DPR-29," Maximum Power Level,"is an editorial correction that changes the Unit 2 designation to Unit 1.
9904120277 990330                 Il                                                                     ;
PDR  ADOCK 05000254                 4                                                                    <
                                                       . g(, h A Unico.n Company

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                ' USNRC;                                   2                              March 30,1999
                 ' SVP-99-001
                  ' Comed requests approval of this amendment by September 30,1999, with a 60 day implementation period. This proposed amendment request is subdivided as follows:
: 1) Attachment A'gives a description and safety analysis of the proposed changes,
                - 2) Attachment B includes the marked-up License pages with the requested changes indicated,
: 3) Attachment C provides information supporting a finding of no significant hazards in accordance with 10 CFR 50.92(c) and, 1
1
: 4) Attachment D provides information supporting an environmental assessment.             1 This proposed amendment has been reviewed and approved by the On-site Plant Operations Review Committee and the Off-site Nuclear Safety Review Board, in accordance with Comed procedures, i
                -' Comed is notifying the State ofIllinois of this application for amendment by            I
                ~ transmitting a copy of this letter and its attachments to the designated State Official.
If there are any questions or comments concerning this letter, please refer them to Mr. Wally Beck, Acting Regulatory Assurance Manager, at (309) 654-2241, extension 3100.
Sincerely,              ,
                                             ~0 L
                - J l P. Dimmette, Jr.'
                   ' ite Vice President Quad Cities Nuclear Power Station i
l Attachments: A. . Description and Safety Analysis of the Proposed Changes
                                  - B. Marked-Up License Pages l                                  C. Information Supporting a Finding of No Significant Hazards L.                                  D. Information Supporting an Environmental Assessment cc:      Regional Administrator- NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

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i i                                                                                         l STATE OF ILLINOIS Docket Nos. 50-254              ;
50-265             i i
l                                                                                         l IN TIIE MATIER OF                                                                 l l
l COMMONWEALTH EDISON COMPANY I
i       QUAD CITIES NUCLEAR POWER STATION - UNITS 1 AND 2 CHANGE TO FACILITY Oa ERATING LICENSES AFFIDAVIT                               I J
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I affirm that the content of this ransmittalis true and correct to the best of my knowledge, information and belie                ,                                 ,
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J.P. 'mmette htsum/f284)
Site ice President i
:                                                                                         \
i l       S"* ascribed and sworn to before me, a Notary Public in and
        ..n the State above named, this         80        day of
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                             " OFFICIAL SEf1" lACA LEE STOERMER                                              :
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7 1
Attachment A Description and Safety Analysis of the Proposed Changes                        I SVP-99-001 (Page 1 of 6) 1 i
A. Summary of Proposed Changes 1
In accordar ce with 10 CFR 50.90, Coned proposes to amend the Licenses at Quad Cities Nuclear Power Station Unit I and Unit 2. The proposed anendment request is administrative in nature. The proposed changes revise the Operating Licenses to delete various license conditions that have been completed, make editorial changes smd provide clarifying information.
B. DescdptY of the Current Requirements
: 1) License Conditions 3.D for DPR-29 and DPR-30, " Equalizer Valve
{
Restriction," requires 'The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation."
Currently, the operational configuration is three of the four valves lased, with one bypass valve open for thermal expansion.
Compliance to the design analysis of this restriction is achieved with closure of one of the two equalizer line valves. Operation with the closure of the two bypass valves does not provide an adequate operational configuration to allow for thermal expansion of water between the two equalizer valves.
: 2) License Conditions 3.M for DPR-29 and 3.L for DPR-30, " Surveillance Requirements," provides certain surveillances were not required to be performed inuemtely upon implenrntation of Amendnent 171 for DPR-29 and Amendment 167 for DPR-30. The surveillance requirements had to be successfully demonstrated prior to entering mode 2 on the first startup following QlRIS and Q2R15, respectively.
: 3) License Conditions 3.N for DPR-29 and 3.M for DPR-30, " Additional Conditions," contained in Appendix C, authorized 6te incorporation into the Updated Final Safety Analysis Report (UFSAR) the description of the Reactor Coolant system design, pressure, temperature and volume that wa:
removed from Technical Specifications Section 5.4, " Design Features."           ;
: 4) License Condition 3.A for DPR-29 (Unit 1), " Maximum Power level,"
cathorizes operation of Quad Cities Unit 2 at power levels not in excess of 2511 megawatts (thermal).
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l                                               Attachment A Description and Safety Analysis of the Proposed Changes SVP 99-001 (Page 2 of 6) l C. Bases for the Curant Requirements
: 1) License Conditions 3.D for DPR-29 and DPR-30, " Equalizer Valve                  l Restriction," established the requirements for the operation of both units with a closed valve in the equalizer line between the two recirculation loops. This was necessary to confonn with the Emergency Core Cooling System (ECCS) evaluati'm which assuned the largest reeirculation line break was 4.2 square feet. Confonnance to the ECCS design evaluation requires operation with a closed valve in the equalizer line, Reference (a).
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: 2) License Conditions 3.M for DPR-29 and 3.L for DPR-30, " Surveillance Requirements," deferred certain surveillance demonstrations upon implementation of *e Current Technical Specifications to avoid umlecessary Unit Shutdowr'          mduct these 18 month surveillances.
: 3) License Condiwns 3.N for DPR-29 and 3.M for DPR-30, " Additional Conditions,'' contained in Appendix C, authorized relocation of Reactor Coolant desigr. information from the Technical Specifications Section 5.4 Design Features to the UFSAR.
: 4) License Condition 3.A, " Maximum Power Level," for DPR-29 authorized operation of Unit 1 at Power levels not in excess of 2511 megawatts (thermal).
D. Need for Revision of the Requirement
: 1) License Conditions 3.D for DPR-29 and DPR-30, " Equalizer Valve ILstriction," states that the valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operatian. This described configuration does not provide an adequate operational configuration to allow for thermal expansio, of water between the two equalizer valves.
: 2) Comed pmposes to delete License Conditions 3.M for DPR-29 and 3.L DPR-30 since the license conditions have been satisfied.
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i Atiachment A Description and Safety Analysis of the Proposed Changes SVP 99-001                                        )
(Page 3 of 6)                                     j
: 3) Comed proposes to delete the License Conditions 3.N for DPR-29 and 3.M DPR-30 since the license conditions have been satisfied.
                                                                                                    )
: 4) Comed proposes an editorial change to License Condition 3.A," Maximum Power Level," for DPR-29 to reflect Unit I authorization versus the incorrect )
Unit 2 reference.
E. Description of the Proposed Changes Quad Cities Nucle ir Pcwer Statie< license conditions are proposed to be          3 changed as follows:                                                               j
: 1) 3.D for DPR-29 and DPR-30," Equalizer Valve Restriction," Currently States: "The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation."
Proposed Statement "Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reador operation with one bypass valve open to allow for thermal expansion of water."
: 2) 3.M for DPR-29 Surveillance Requirements Currently States:
                      "The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to oc performed immediately upon implementation of Amendment No.171:
: a. Surveillance Requirements 4.2.A.2," Logic System Functional Test for Isolation Actuation Instrumentation," Table 4.2.A-1, item 2.a. 2.b,2.c,   J and 2.d, Secondary Containment isolation.
: b. Surveillance Requirement 4.9.A.S.h," Emergency Diesel Generator 24 hours test."
: c. Surveillance Requirement 1.9.A.B.c," Emergency Diesel Generator full        i l
load reject test."
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I L.

Attachment A Description and Safety Analysis of the Proposed Changes SVP-99-001 (Page 4 of 6)
The above Surveillarce Requirenrnts hall be successfully denenstrated prior to entering into MODE 2 on the first plant startup following the fifteenth refueling outage (Q1R15)."
P.roposed Statement 3.M Deleted 3.L for DPR-30 Surveillance Requirenents Currently States:
              'The Surveillance Requirenrnts contained in the Appendix A Technical Specifications and listed below are not required to be perfonned imnrdiately upon implementation of Anrndarnt No.167:
: a. Surveillance Requirement 4.2.A.2, " Logic System Functional Test for Isolation Actuation Instrumentation," Table 4.2.A-1, Item 4.a, Reactor Water Cieanup (RWCU) isolation on Standby Liquid Control (SBLC) initiation.
: b. Surveillance Requirement 4.2.A.2, " Logic system Functional Test for Isolation Actuation Instrumentation," Table 4.2. A-1, Item 2.a,2.b,2.c, and 2.d, Secondary Contauunent isolation.
: c. Surveillance Requirement 4.9.C.2, " Logic System Functional Test for Anticipated Transient Without Scram (ATWS) - Recirculation Pump Trip (RPT)."
: d. Surveillance Requirement 4.1.A.1, " Turbine Stop Valve, Closure, RPS Calibration," Table 4.1. A-1, Item 9.
The above Surveillance Requirements shall be successfully demonstrated       i prior to entering into MODE 2 on the first plam startup following the fifteenth refueling outage (QlR15)."
Proposed Statement 3.L Deleted
: 3) 3.N for DPR-29 and 3.M for DPR-30, " Additional Conditions," contained in Appendix C, Currently States:
1
              'The additional conditions contained in Appendix C, as revised through       j Amendment No.177 (Unit 1) and Amendment No.175 (Unit 2), are hereby          ,
incorporated into this license. Comnunwealth Edison Company shall operate the facility in accordance with the Additional Conditions."
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Attcchment A Description and Safety Analysis of the Proposed Changes                      l SVI 9 001                                           4 (Page. c 6)
Appendix C CurrentlyJtates:
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                 " Implementation Date - 60 days from the date of issuance."
This amendment authorizes the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) the description of the Reactor Coolant system design pressure, temperature and volume that was removed from Technical Specification Section 5.4, and evaluated in staff safety evaluation dated May 23,1997.
Proposed Statements 3.M for DPR '9 and 3.N for DPR-30 None as revised through Amendment No. . .
Proposed Statements Appendix C for DPR-29 and DPR-30 None 1
: 4) Quad Cities Nuclear Power Station License Condition 3.A for DPR-29 is proposed to be changed as follows:
3.A for DPR-29 Maximum Power Level Currently States:                            !
                 " Commonwealth Edison is authorized to operate Quad Cities Nuclear Power Station Unit No. 2 at power levels not in excess of 2511 megawatts (thermal)."
Proposed Statement for 3.A DPR-29," Commonwealth Edison is authorized to operate Quad Cities Nuclear Power Station Unit No. ] at power levels not in excess of 2511 megawatts (thermal)."
F. Safety Analysis of the Proposed Changes
: 1) The changes proposed by this license amendment request are administrative in nature. The purpose of the proposed change is to clarify the operational configuration which allows for thermal expansion of water between the two equalizer line valves. Our previously approved license amendments 25 and 12 for Quad Cities Nuclear Power Station, Unit I and Unit 2 approved-opeiation with a clwed equalizer line valve to conform with the ECCS design evaluation. This was not clearly described in the license conditions that implemented this requirement. The proposed change accurately desc:ibes the plant configuration which is more conservative than the design analysis. The proposed change will require :wo equalizer valves and one bypass valve to be

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!                                         Attachment A l                 Description and Safety Analysis of the Proposed Changes l                                          SVP-99-001
         ,                                 (Page 6 of 6) closed as compared to a single closed equalizer valve required by our design evaluation. The single equalizer line hypass valve being open during operation enhances overall plant safety by allowing thermal expansion of water between the equalizer line valves. This configuration prevents an undesirable pressure buildup between the equalizer line valves.
i The proposed change provides adequate operational flexibility while maintaining the design bases of the facility. This represents an enhancement to overall plant safety by providing a clear description of the pl.mt configuration and minimizes the potential for an undesirable pressure increase between the equalizer line valves.
: 2) 3.M for DPR-29 and 3.L for DPR-30, " Surveillance Requirements"
: 3) 3.M for DPR-29 and 3.M for DPR-30," Additional Conditions Appendix C" These license conditions were one-time commitments that have been satisfied.
The changes are administrative and only provide updated information. No physical or operational change to the facility will result from the proposed changes.
: 4) 3.A. for DPR-29, " Maximum Power Level" This proposed license condition change is administrative and only provides an editorial change. No physical or operational changes to the facility will result fmn3 fir proposed changes.
G. IMPACT ON PREVIOUS SUBMITTALS Comed has reviewed previous submittals and has concluded the proposed change has no impact on previous submittals currently under NRC review.
H. SCHEDULE REQUIRMENTS Comed requests NRC approval of this request by September 30,1999, to be effective no 1.ater than 60 days following approval.}}