View source for B16902, Application for Amend to License DPR-65,changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atomspheric Steam Dump Valves

{{Adams
| number = ML20236Y079
| issue date = 08/04/1998
| title = Application for Amend to License DPR-65,changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atomspheric Steam Dump Valves
| author name = Bowling M
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = B16902, NUDOCS 9808110154
| package number = ML20236Y081
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 11
| project = 
| stage = Request
}}

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NdM                                                                                                 ""P" F'"r "d-  ("""'' '56)' *"''''"'d' "' "385 Nudear Energy                                                                                       uasior., suacar power station Northeast Nuclear Energy Coinpany P.O. Hos 128 Waterford, CF 06385-0128 l                                                                                                                 (860) 447-1791 l                                                                                                                 Fax (800) 444-4277 l
i                                                                                                                 The Northeaat Utilitic Systern AS        4 1998 t
Docket No. 50-336
:                                                                                                                                                B16902 1
Re: 10CFR50.90 U.'S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 M!ilstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Condensate Storace Tank and Atmospheric Steam Dumo Valves Introduction Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License DPR-65 by incorporating the attached proposed                                                                           ;
changes into the Technical Specifications of Millstone Unit No. 2. NNECO is proposing                                                                       !
to change Technical Specification 3.7.1.3, " Plant Systems - Condensate Storage Tank"                                                                       ;
and to add Technical Specification 3.7.1.7, " Plant Systems - Atmospheric Steam Dump                                                                        !
Valves."    information will be added to the Bases of the associated Technical Specifications to address the proposed changes.                                                                                                             l Attachment 1 provides a discussion of the proposed changes and the Safety Summary.
Attachment 2 provides the Significant Hazards Consideration. Attachment 3 provides                                                                          !
the marked-up version of the appropriate pages of the current Technical Specifications.
Attachment 4 provides the retyped pages of the Technical Specifications.
The proposed change to the Technical Specification Index is on the same page (Vill) which has been proposed to be changed in a separate {{letter dated|date=July 21, 1998|text=letter dated July 21, 1998}}.
The proposed change to Technical Specification Bases Section B 3/4.7.1 is on the same page (B 3/4 7-3 which has been proposed to be changed in separate letters dated April 6,1998,* ) July 21.,1998,                                                  and July 30,1998.* The proposed changes
;       m      M. L Bowling, Jr. letter to the NRC, " Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Reactor Protection and Engineered Safety Features Trip Setpoints," dated July 21,1998.
       ,m      M. L Bowling, Jr. letter to the NRC, " Millstone Nuclear Power Station, Unit No. 2 l                                                                                                                                                               ,
4,,,;y     9 Proposed Revision to Technical Specifications Compliance issues Number 3," dated
  + ' V a v 8- April 6,1998.                                                                                                                                  t E s qgggg ggggg ,                                                           y                                                            7&               \
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l        U.S. Nucl:rr Regulatory Commission B16902/Pcga 2 L
contained in this letter do not assume approval of any of the previously submitted changes.-
Environmental Considernlions l
NNECO has reviewed the proposed License Amendment Request against the criteria of 10CFR51.22 for environmental considerations. The proposed changes modify the
;        minimum required volume in the Condensate Storage Tank and add a new Technical Specification to cover the Atmospheric Steam Dump Valves. These changes do not increase.the type and amounts of effluents that may be released off site. In addition, this amendment request will not significantly increase individual or cumulative occupational radiation exposures. Therefore, NNECO has determined the proposed L        changes will n-t have a significant effect on the quality of the human environment.
l        Conclusions The proposed changes were evaluated utilizing the criteria of 10CFR50.59 and were i        determined not to involve an unreviewed safety question. Additionally, we have concluded the proposed changes are safe.
The proposed changes do not involve a significant impact on public health and safety l        1see the Safety Summary provided in Attachment 1) and do not involve a Signncant Hazards Consideration pursuant to the provisions of 10CFR50.92 (see the SignFicant Hazards Consideration prcvided in Attachment 2).
Plant Ooerations Review Committee and Nuclear Safety Assessment Board The Plant Operations Review Committee and Nuclear Safety Assessment Board have reviewed and concurred with the determinations.
Schedule We request issuance at your earliest convenience, with the amendment to be implemented within 60 days of issuance.
State Notification in accordance with 10CFR50.91(b), a copy of this License Amendment Request is being pruvided to the State of Connecticut.
D)
M. L. Bowling, Jr. letter to the NRC, " Millstone Nuclear Power Station, Unit No. 2 Changes to Technical Specifications Bases Resolution of Miscellaneous Condition Reports," dated July 30,1998.

U.S. Nucl=r Regulatory Commission B16902/Page 3 i
jL           if you should have any questions on the above, please contact Mr. Ravi Joshi at l            (860) 440-2080.
I Very truly yours,
: l.                                                                                           NORTHEAST NUCLEAR ENERGY COMPANY Y
M. L Bowling, Jr.                                t/
Recovery Officer - Technical Services l.
)            Sworn to and subscribed before me l            this YCday of Oi,,o,M                                                           .1998
                  @tet:L         .
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!                              ary Pubic My Commission expires //3/[200o l
l            Attachments (5) l cc:    H. J. Miller, Region I Administrator D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, Ph.D, Director - Special Projects Office W. D. Lanning, Deputy Director of Inspections - Special Projects Office I'                  P. F. McKee, Deputy Director of Licensing - Special Projects Office Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 t
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Docket No. 50-336 B16902 l-i.
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Attachment 1 i
Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications l                                                                                                      Condensate Storage Tank and Atmospheric Steam Dump Valves Discussion of Proposed Changes i
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August 1998 L_ ____    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - -                 -- -   - - - - -      - - - - - -- - - - - - _ _ _ _ _ . - - - - _ _ _ _ _ - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _

U. S. Nucl:ar Regulatory Commission B16902/Attechm:nt 1/Paga 1
;                                                                                                                      Proposed Revision to Technical Specifications i
Condensate Storage Tank and Atmospheric Steam Dump Valves Discussion of Proposed Changes Introduction -
Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License DPR-65 by incorporating the attached proposed changes into the Technical Specifications of Millstone Unit No. 2. NNECO is proposing to change Technical Specification 3.7.1.3, " Plant . Systems - Condensate Storage Tank" and to add Technical Specification 3.7.1.7, " Plant Systems - Atmospheric Steam Dump Valves."
!'                                                              information will be added to the Bases of the associated Technical Specifications to address the proposed changes.
l                                                               Description of Proposed Chanoes l
Condensate Storage Tank Technical Specification 3.7.1.3 will be modified to increase the minimum required Condensate Storage Tank (CST) level from 150,000 gal'ons to 165,000 gallons. This l                                                              increase is necessary to account for discharge nozzle pipe elevation above tank bottom i                                                              and vortex formation.- The Bases will be expanded to provide more specific details concerning the required CST volume.
This proposed change will ensure sufficient water volume is maintained in the CST for l                                                              use by the Auxiliary Feedwater (AFW) System. The required CST volume is based on the following three requirements.
!                                                                                                   1.            Remove decay heat and sensible heat to cool down the plant to < 300 F.
l                                                                                                   2.            Remove only decay heat to maintain the r! ant in hot standby for 10 hours.
: 3.            Remove decay heat and sensible heat to cope with an 8 hour Station Blackout (SBO) event.        #
l                                                             The C-ST volume required to satisfy each of these requirements is summarized in Table l                                                               1. These values have been determined using the 1979 ANS Decay Heat Standard.
(Note: The volumes listed are approximations.)
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U. S. Nuc1=r Rcgulatory Commission l                                 B16902/ Attachment 1/Page 2 l
l                                                                       TABLE 1 CST VOLUME REQUIREMENTS l
i EVENT        USABLE                                                          NOZZLE    NOZZLE    TOTAL VOLUME                                                         ELEVATION VORTEXING VOLUME l
Loss of       136,000                                                         15,000    8,000    159,000 Offsite l                                     Power 10 Hours       115,000                                                         15,000    8,000    138,000 Hot Standby Station       136,000                                                         15,000    8,000    159,000 Blackout Atmospheric Steam Dump Valves Technical Specification 3.7.1.7, " Plant Systems - Atmospheric Steam Dump Valves,"
will be added. The Atmospheric Steam Dump Valves (ASDVs) would be used to remove heat from the Reactor Coolant System (RCS) to either maintain hot standby conditions or cool down to Shutdown Cooling (SDC) entry conditions if the condenser steam dump valves are not available. Therefore, the operability of the ASDVs should be required by Technical Specifications.
The proposed specification, 3.7.1.7, is based on Technical Specification 3.7.4,
                                  " Atmospheric Dump Valves (ADVs)," of NUREG - 1432, # Standard Technical Specifications Combustion Engineering Plants," Vol. 1, Rev. 1. The proposed specification has been modified from the standard specification to reflect the plant configuration of Millstone Unit No. 2 and expected plant operation with inoperable ASDVs. The proposed specification is consistent with NUREG - 1432.
Safety Summary Condensate Storage Tank The minimum required usable CST water volume is sufficient to address the following two scenarios:
: 1.      Remove decay heat and sensible heat to cool down the plant to < 300 F following a loss of offsite power. This will require a usable volume of l                                         approximately 136,000 gallons.
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: 2.      Remove only the decay heat associated with maintaining the plant in Hot Standby for 10 hours. This will require a usable volume of approximately 113,000 gallons, l
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U. S. Nuclatr Regulatory Commission B16902/ Attachment 1/Page 3 Two factors have been considered to determine the unusable volume of water in the CST.
: 1.      Volume of water below the top of the tank nozzle - approximately 15,000 gallons.
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: 2.      Vortex formation in the CST at the AFW supply piping entrance - approximately 8,000 gallons                                                                                                     (
l The total unusable volume for the loss of offsite power event is approximately 23,000                                     l gallons. The minimum required Technical Specification volume is approximately 159,000 gallons (136,000 + 23,000) to ensure the capability to remove decay heat and sensible heat to cool down the plant to < 300 *F following a loss of offsite power. This is the most limiting case.
The total unusable volume for the removal of only decay heat for 10 hours is also approximately 23,000 gallons. The minimum required Technical Specification volume i                                             is approximately 138,000 gallons (115,000 + 23,000) to remove decay heat to maintain i                                             the plant in Hot Standby for 10 hours.
An SBO event is also a consideration for the quantity of water to maintain in the CST.
l                                             Millstone Unit No. 2 is required to be able to cope with an 8 hour SBO event. This requirement is bounded by the cooldown scenario previously discussed. The required CST volume for an SBO event is approximately 159,000 gallons (136,000 + 23,000).
CST water volume requirements for Appendix R concerns are bounded by the l                                             previously discussed scenarios because makeup to the CST from the Fire Water l
System is assumed.
The proposed change to increase the minimum required CST level of Technical Specification 3.7.1.3 will ensure sufficient water is available for use by the AFW l                                             System. The proposed increase to 165,000 gallons, which includes an additional approximate 6,000 gallons of margin, is within the CST capacity of 250,000 gallons, is
!                                             protected by the concrete missile shielding (205,000 gallon level), and is below the normal operating level. Therefore, there is no significant impact on public health and l
safety.
Atmospheric Steam Dump Valves The proposed change to add a Technical Specification for the ASDVs will provide additional assurance that the ASDVs will be available to either maintain the unit in hot standby, or cool down the unit to SDC entry conditions if the condenser steam dump valves are not available. Therefore, there is no significant impact on public health and safety.
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l                                                               U. S. Nuclerr Regulatory Commission i                                                               B16902/Atttchm:nt 1/Page 4 The proposed changes have no adverse effect on how any of the associated systems                                             i or components function to prevent or mitigate the consequences of design basis                                               i accidents. Also, the proposed changes have no adverse effect on any design basis                                             I accident previously evaluated. Therefore, there is no adverse impact on public health and safety.
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(                                                                                  Docket No. 50-336 i                                                                                            B16902 l
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l Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Condensate Storage Tank and Atmospheric Steam Dump Valves Significant Hazards Consideration August 1998

U. S. Nucis r R:gulatory Commission B16902/Attrchment 2/Pega 1 Proposed Revision to Technical Specifications Condensate Storage Tank and Atmospheric Steam Dump Valves Significant Hazards Consideration Significant Hazards Consideration in accordance with 10CFR50.92, NNECO has reviewed the proposed changes and has concluded that they do not involve a significant hazards consideration (SHC). The l
basis for this conclusion is that the three criteria of 10CFR50.92(c) are .not compromised. The proposed changes do not involve an SHC because the changes would not:
: 1.      Involve a significant increase in the probability or consequences of an accident previously evaluated.
                                                                                                                       ]
The proposed change to increase the minimum required Condensate Storage Tank (CST) level of Technical Specification 3.7.1.3 will ensure sufficient water is available for the Auxiliary Feedwater (AFW) System to function as designed to mitigate design basis accidents. There will be no adverse effect on equipment important to safety. Therefore, the proposed change will not result in a significant increase in the probability or consequences of an accident previously evaluated.
i The proposed change to add a Technical Specification for the Atmospheric j              Steam Dump Valvas (ASDVs) will provide additional assurance that the ASDVs                              j will be available to either maintain the unit in hot standby, or cool down the unit                      I to Shutdown Cooling (SDC) entry conditions if the condenser steam dump                                  I valves are not available. The proposed change does not alter the way any structure, system, or component functions. There will be no adverse effect on any i
design basis accident previously evaluated or on any equipment important to safety. Therefore, the proposed change will not result in a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes have no adverse effect on any of the design basis accidents previously evaluated. Therefore, the license amendment request does not impact the probability of an accident previously evaluated nor does it involve
!              a significant increase in the consequences of an accident previously evaluated.
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U. S. Nucigar Regulatory Commission B16902/Attachm:nt 2/Prgo 2
: 2.                   Create the possibility of a new or different kind of accident from any accident previously evaluated.
l The proposed changes will not alter the plant configuration (no new or different type of equipment will be installed) or require any new or unusual operator actions. They do not alter the way any structure, system, or component functions and do not alter the manner in which the plant is operated. The proposed changes do not introduce any new failure modes. Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.
: 3.                   Involve a significant reduction in a margin of safety.
l The proposed change to increase the minimum required CST level will ensure the AFW System will function as designed to mitigate design basis accidents.
The proposed change to add a Technical Specification for the ASDVs will provide additional assurance that the ASDVs will be available, if needed. There will be no adverse effect on equipment important to safety. Therefore, there will be no significant reduction of the margin of safety as defined in the Bases for the Technical Specifications affected by these proposed changes.
The NRC has provided guidance conceming the application of standards in 10CFR50.92 by providing certain examples (March 6, 1986, 51 FR 7751) of amendments that are considered not likely to involve an SHC. The changes proposed herein to increase the minimum required water volume in the CST and to add a Technical Specification to cover the ASDVs are enveloped by example (ii), a change that                                                                                                                          i constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications.
As described above, this License Amendment Request does not impact the probability of an accident previously evaluated, does not involve a significant increase in the consequences of an accident previously evaluated, does not create the possibility of a new or different kind of accident from any accident previously evaluated, and does not result in a significant reduction in a margin of safety. Therefore, NNECO has concluded that the proposed changes do not involve an SHC.
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