ML20070M005

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Application for Amend to License NPF-3,changing TS 3.0.3 & 3.0.5 to Revise Time Interval for Achieving Hot Standby (Mode 3) & Increasing Time Interval for Reading Hot Standby from 6 H to 7 H Once TS 3.0.3 Entered
ML20070M005
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/18/1991
From: Shelton D
CENTERIOR ENERGY
To:
Shared Package
ML20070M004 List:
References
NUDOCS 9103210007
Download: ML20070M005 (6)
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Text

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Dock t Number 50-346

  • Lic:ns3 Number NPT-3

. . 5: rial Nu2b:r 1848

' Enclosure Page 1 APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NUMBER NPF-3 DAVIS-BESSE NUCLEAR POVER STATION UNIT NUMBER 1 Attached are the requested changes to the Davis-Besse Nuclear Power Station, Unit Number 1 Facility Operating License Number NPF-3. Also included are the Safety Assessment and-Significant Hazards Consideration.

The proposed changes (submitted under cover letter Serial Number 1848)

  • concern:

Technical Specifications: 3.0.3 and 3.0.5, Limiting Conditions for Operation -  !

Applicability.

Bases 3/4.0, Applicability.

By -

D. C. Shelton, Vice Presiden't - Nuclear-Sworn and' subscribed before me- this 18th day of March,1991. >

td fubI _ Alb1 Notsty Public, State of Ohio-EVELYNLORES8' t IRAMPUBUG.8 TATE OF0HO 40esahdonEghsA418,1m L

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i 9103210007 910310 PDR ADOCK0500g6 P

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Dockot Nu:bar 50-346 Licensa Numb 2r NPF-3

. . S2 rial Numbar 1848 Inclosure l Page 2 The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station, Unit Number 1, Operating License Number NPF-3 Appendix A, Technical Specification (TS) 3.0.3 and 3.0.5, Limiting conditions for Operation - Applicability:

A. Time required to implement: This change is to be implemented within 45 days after the NRC issuance of the license amendment.

B. Reator, for Change (License Amendment Request Number 90-0041):

This change affects TS 3.0.3 and 3.0.5, Limiting conditions for Operation - Applicability, by revising the allovable time interval for achieving HOT STANDBY (Hode 3). The proposed change to TS 3.0.3 vould increase the allowed time interval for achieving HOT STANDBY from six hours to reven hours once TS 3.0.3 has been entered. A minor editorial correction is also proposed to this Technical Specification.

Corresponding changes have been proposed to Technical Specification Bases 3.0.3. A similar change is proposed to Technical Specification 3.0.5 to increase the time interval from six hours to eight hours allowed for reaching HOT STANDBY once Technical Specification 3.0.5 has been entered.

C. Safety Assessment and Significant Hazards Consideration: See Attachment 1.

i l

Dock 0t Nu;b;r 50-316 Lic;nse Nu:b:r NPF-3

. Serici Nu b r 1848

' Attachment Page 1 SATETY ASSESSMENT AND SIGNITICANT HAZARDS CONSIDERATION FOR LICEN;E AMENDMENT REQUEST NUMBER 90-0041 TITLE Revision of Technical Specifications 3.0.3 and 3.0.5, Limiting conditions for Operation - Applicability.

DESCRIPTION The purpose of the proposed changes is to modify the Davis-Besse Nuclear Power Station (DBNPS) Operating License NPT-3, Appendix A. Technical Specifications (TS's). Attached are the proposed marked-up changes to the TS's. The proposed changes effect TS 3.0.3 and 3.0.5, Limiting condition for Operation by revising the allovable time interval for achieving HOT STANDBY (Hode 3). Upon entry into existing TS 3.0.3, unless associated ACTION requirements are met within one hour, action shall be initiated to place the plant in an operational mode in which the applicable Limiting Condition for Operation does not apply, by placing it in at least HOT STANDBY vithin six hours. The six hour interval starts immediately when TS 3.0.3 is entered. The proposed change to TS 3.0.3 to require reaching HOT STANDBY vithin the "next six hours" [added emphasis]

vould in effect, increase this six hour interval to seven hours. A minor editorial entrection is also proposed to this TS. Corresponding changes have been proposed to TE Bases 3.0.3.

Existing TS 3.0.5 requires that within two hours of a system, subsystem, train, component or device being declared inoperable solely because 1) its normal power source and emergency power source are inoperable, or 2) its normal power source or. emergency power source is inopernble and its redundant system, subsystem, train, component or device is inoperable, actions must be initiated to achieve HOT STANDBY vithin six hours. This six hour interval starts immediately when TS 3.0.5 is entered. The amendment request proposes revising the allovable time interval to state within the "next six hours" (added emphasis] thereby effectively increasing the interval by two hours.

These proposed TS changes are based on the guidance provided by the Standard TS's for Babcock and Vilcox Pressurized Vater Reactors, NUREG-0103, Revision 4, and are consistent with model TS 3.0.3 provided in Generie Letter 87-09, Sections 3.0 and 4.0 of the Standard Technical Specification (STS) on the Applicability of Limiting Conditions for Operating and Surveillance Requirements, dated June 4, 1987 (Toledo Edison letter Log Number 2326). The proposed changes to Bases 3.0.3 are similar to the wording in the Vestinghouse Standard TS's, HUREG-0452, Revision 4.

SYSTEMS, COMPONENTS AND ACTIVITIES AFFECTED The activities affected by these proposed changes are the time limits allowed f or reaching HOT STANDBY under TS's 3.0.3 and 3.0.5. There are no hardvare l

systems or components affected by these proposed chsnges.

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l

Dockot Number 50-346 L

License Number NPT-3

. , Serici Numb 2r 1848 Attachment Page 2 SATETY TUNCTIONS OF THE AFFECTED SYS1 EMS, COHp0NENTS, AND ACTIVITIES TY safety function of TS's 3.0.3 and 3.0.5 is to provide for shutdown of the

.lant due to equipment inoperability which places the plant outside the Limiting Conditions for Operation, including the associated ACTION statements.

TS 3.0.3 specifies a six hour tirne limit for reaching HOT STANDBY vhen a Limiting Condition for Operation is not met and the associated ACTION are not met vithin the specified tirne interval. This requirements, specifiestion alsoif any, del TE ntes the action to be taken for circumstances not directly provided for in the ACTION statements when the Limiting Condition for Operation is not met. The function of TS Bases are to explain the reasons for a 15.

TS 3.0.5 specifies that when a syrtem, subsystem, train, component or device is determined to be inoperable only because its normal power source is inoperable or its emergency power is inoperable, it may be considered OPERABLE, provided its redundant system or component is OPERABLE vith an OPERABLE normal or emergency power source.

If these conditions are not satisfied, then the plant must be in HOT STANDBY vithin six hours of entering TS's 3.0.3 or 3.0.5.

EFFECTS ON SATETY One hour is provided by TS 3.0.3 to prepare for an orderly shutdovn before initiating a change in plant operation. This time permits the operators to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lover modes of operation permit the shutdown to proceed in a controlled snd orderly manner tSat is within the specified max. mum cooling rate and within the cooldown capabilities of the plant assuming only the minimum required equipment is operable. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems.

The effect of the proposed changes to TS 3.0.3 and its Bases is to increase the maximum time interval from six hours to seven hours allowed for reaching HOT STANDBY once TS 3.0.3 has been entered. This change is consistent with the guidance of Babcock and Vilcox Standard TS's for Pressurized Vater Reactors, NUREG-0103, Revision 4, and the model TS's included in Generic Letter 87-09, which also allow for a maximum of seven hours. The basis for the time interval of seven hours is to reasonably allov for an orderly shutdown and not challenge safety systems. In the Nuclear Regulatory Commission's (NRC) Safety Evaluation for License Amendment Number 71 (Toledo Edison letter Log Numbet 1552, dated July 18, 1984) to the DBNPS Operating License, the NRC noted that DBNPS TS 3.0.3 vas only six hours while the appli:able Standatd Ts's allnved m en hours. Since the proposed change is within the bounds judged to be tearonably acceptable for nuclear power plants and there are no factors which would cause the DBNPS to take exception, there is no effeet on safety.

Docket Nu bar 50-346 h . Licensa Nuxbor NPP-3

  • . Serial Nonbar 1848 l

'Attachsent l Page 3 The effect of the proposed change to TS 3.0.5 is to increase the time interval  !

4 from six hours to eight hours allowed for reaching HOT STANDBY once TS 3.0.5 has been entered. This change is consistent with the guidance of the Babcock f and Vilcox Standard TS's which allow for a maximum of eight hours. The basis i for the time interval of eight hours is to reasonably allow for an orderly shutdown and not challenge the safety systems. Since the proposed change is within the bounds judged to be reasonably acceptable for nuclear power plants and there are no factors which would cause the DBNPS to take exception, there is no effect on safety.

SIGNIFICANT HAZARDS CONSIDERATION

' The NRC has provided standards in 10 CFR $0.92(c) for determining whether a significant hazard exists due to a proposed amendment to an Operating License for a facility. A proposed amendment involves no significant hazards consideration if operation of_the facility in accordance with the proposed changes voulds (1) Not involve a significant increase in the probs.bility or i

4 consequences of an accident previously evaluated; (2) Not create the .

possibility of a new or different kind of accident from any. accident previously evaluated 1 or (3) Not involve a significant reduction in a margin of safety.

Toledo Edison has reviewed the proposed changes and determined that a- '

significant hazards consideration does not-exist because operation of the DBNPS Unit Number 1, in accordance with these change would la.- Not involve a'significant increase in the probability of an accident-previously evaluated because no initiators or assumptions for a previot; sly evaluated accident are significantly affected, by these proposed changes to TS's 3.0.3, 3.0.5 and Bases 3.0.3.

Ib. Not involve ~a significant increase in the consequences of an accident  ;

previously evaluated because no initiators or assumptions for a previously evaluated accident are significantly affected by these proposed changes to TS's 3.0.3, 3.0.5 and Bases 3.0.3.

-2a. Not create the possibility of a new kind of accident previously evaluated because no accident initiators are created. No new hardware changes are being made, no new testing is being created and no new operating manipulations are being created by these proposed changes to TS's 3.0.3, 3.0.5 and Bases 3.0.3.

2b.- Not create the possibility et a different kind of-accident from any accident previously evaluated because no accident initiators are created.

No changes in hardware, tecting, or plant manipulations are being created by these proposed changes to TS's - 3.0.3, 3.0.5 and Bases 3.0.3.

3. -Not involve a significant reduction in a margin of safety because the ,

proposed changes to TS's 3.0.3, 3.0.5 and Bases 3 0.3 are consistent with '

-the margin of safety established for nuclear power plants of the DBNPS type in the Babcock and Vilcox Standard Technical Specifications for Pressurized Vater Reactors, NUREG-0103, Revision 4. There is no reason for the associated time intervals to be more restrictive for the DBNPS.

. _= . _ _ ._ _ __. .

DockOt Nu:ber 50-346

,- . Lie nse Nurber NPP-3

. . Sarici Nurb:r 1818 Attachment Page 4 CONCLUSION On the basis of the above, Toledo Edison has determined that this License Amendment Request dots not involve a significant harards consideration. As this License Amendmett Request concerns a proposed change to the TS's that must be reviewed by the NRC Commission, this License Amendiuent Request does not constitute an unreviewed safety question.

ATTACHMENT Attached are the proposed marked-up changes to the Operating 1.icense.

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