ML20005E807

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Proposed Tech Specs Removing Table 3.6-2, Containment Isolation Valves.
ML20005E807
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/22/1989
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20005E803 List:
References
1737, NUDOCS 9001110090
Download: ML20005E807 (14)


Text

. _ . _ .._. - _ _ _ _ . _ _. _ _ _ _ _ - _ . _ . _ _ . _ _ . _ _ _ __ _ _

M Docket Number 50-346 -

License Number NPF-3 Serial Number 1737- '

)

Attachment 1 l Page 4  ;

DEFINITIONS REPORTABLE EVEtri' l.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions are either:

1.

Capable or of.being closed by the Safety Features Actuation System, 7v s_._ s -

/ 2.

Closed by manual valves, blind flanges, or deactivated automatic i valves secured in their closed positions, except - pr: tid:d ia-T .th 2 ' 2 e' @;i -- -' -- ' ' ' '

%se afprove<l -lo be, own un&r odmirustadWe. cgonire i

b. All equipment ha M Iosed and sea c.- Each airlock is OPERABLE pursuant to Specification 3.6.1.3,
d. The containment leakage rates are within the limits of Specification 3.6.1.2, and "

e.

The sealing mechanism associated with each penetration (e.g., velds, bellows or 0-rings) is OPERABLE.

CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel l=

output such that it responds with necessary range and accuracy to known values of,the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alara and/or trip i

functions, and shall include the CHANNEL PUNCTIONAL TEST. CHANNEL CALIBRATION any be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall bt_the qualitative ass 4Jssent of channel behavior during operation by observation. This determination shall include, where i

possible, comparison of the channel indication and/or status with other l indications and/or status derived from independent instrument channels measuring -

the same parameter.

DAVIS-BESSE, UNIT 1 1-2 Amendsent No. /97.135

[Of P

b [C

~I

- Docket Number;50-346'

License Number.NPF-3 i I

, ' Serial Number 1737 Attachment I Page 5-3/4.6 CONTAINMENT SYSTEMS 3/4.6.1- PRIMARY CONTAINMENT CONTAINMENT INTEGRITY i

LIMITING CONDITION FOR OPERATION l.

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

1

. APPLICABILITY: MODES 1, 2, 3 and 4.

p ,

l' ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l

and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />..

l SURVEILLANCE REQUIREMENTS , 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

! a. At least once per 31 days by verifying that:

p ,.. s ~ - ~ ~w~ y l- 1. All penetrations

  • not capable of.being closed by OPERABLE (

containhlent automatic isolation valves.and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except :: p m; W d ia Tdle 3.5 2 Of -i 3 bc Sr:f ficsti;;Am.5.3.1, cj'ene un&co  ;;S h5c vctkes %d 1in,shtve cotwa gpuiSM All equipment hatchehre closeo and sealedW,c,3,g Q 2.

Q

b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

L *Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured 'i. the closed position. These penetrations shall be verified closed dt.rics each COLD SHUTDOWN except that verification of these penetrations being closed need not be perfonned more often than once per 92 days.

DAVIS-BESSE, UNIT 1 3/4 6-1 (1

gDocket Number _50-346: ,

tLic nsa Number NPF-3' N i Serial Number 1737-Attachment 1 --

}Page6 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES HioiOSED SUIaINO ld ' I3i0.8 BY LETii.h LIMITING CONDITION FOR OPERATION All - -

3.6.3.1 - .h containment isolation valves :p;;ifhd in Teble 3.0-b shall be OPERABLE with isolation timesa: br i, T;bh 3.0-2.- /e.s3 M TdMM

  • ACTION:

~ - ~ .

dith one or more of the isolation valve (s) :;nified E T:bh 3.5 [

inoperable, either: y

a. -Restore the inoperable valve (s) to OPERABLE status.within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or (f b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of

. at least one deactivated automatic valve secured'in the isolation -

position, or t b c.

b Isolate each affected penetration within 4-hours by use of at least one closed manual valve or blind flange; or

d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

1 SURVEILLANCE REQUIREMENTS ~

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g gg g)y

              ,               4.6.3.1.1    The isolation valves :;=i' icd '- T:bk 3.0 2 shall be                   ,

the valve.to service after demonstrated naintenance, OPERABLE repair prior or replacement to returningis work performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

        ,                     f $a.rve tllout 4edth ed M L/es Ads 100 AA6 (ol) ICSIlh d Tc6116 is ned re tred prior 4 ederin]y MODE 4 b d dhdl be- pa6<wd prtoc 4e en4um M6DE 3<

kk The 7tcMtm ed 6pede

  • 3.0,4 are wcN g\tcMc..
                                   %eted vdves m k oped % iWerwtte d basis N        s    Rhdy Adm t Pl'6 hq       oNC C         Ck' w~            ~ ~ . - - -               . - -         -     _     ,_

DAVIS-BESSE, UNIT.1 3/4 6-14 _ ' '

t, c .

                               ~

g Dock t Numbar 50-346

          > Lic: ion Number NPF-3
 ): f ~

iScrial Number 1737-Attachment 1 g

    ,      Page 7.

o ,

t. -l CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) m .p- W w u x.- % -
                                                                                           - s. .

4.6.3.1.2 Each isolation valve -:; :ified t--T2ic 3.5 2 shall be- , demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at i least once per 18 months by: .j m

                                                                ~~
a. Verifying that on a containment isolation test signal, each automatic isolation valve actuates to its isolation position. i
b. Verifying that on a Containment Purge and. Exhaust isolation  !

test signal, each Purge and Exhaust automatic valve actuates i to its isolation position. ,

                                                                                                  ~

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                                                                                                        \

l L 1 DAVIS-BESSE, UNIT 1 3/4 6-15

4 - k)t>ck;t Numb:r 50-346'

d.
  • Licin:e Number NPF-3 Serial Number 1737.

Attachment 1- 3, (,, - 1

           '*S*
  • T)f6LC CcdMIAIMEA)T .2 Sou97RAI VM VE5 3 ILETED '

TABLE 3.6-2 o CONTAINMENT ISOLATION VALVES PENETRATION VALVE I LATION MBER NUMBER FUNCTION TIME j (seconds) A, ONTAINMENT ISOLATION 1 RC240A Pressurizer Sample Line 30 1 RC240B Pressurizer Sample Line 30 2 # 607 Steam Generator Seconda Water Sample Line 10 CC14 A: Component Cooling W er Inlet Line 3 15~ 3 CC1411B Component Cooling ater Inlet Line 15 4 CC1407A 15 mponent Coolji g Water Outlet Line 4 CC1407B Com onent Co Ting Water Outlet- Line 15 8A CV5070 Conta men Vessel Vacuum Breaker 15 8B CV5071 Contain t Vessel Vacuum Breaker 15 8C CV5072 Contapmen Vessel Vacuum Breaker 15 . 8D CV5073' Con finment ssel Vacuum Breaker , 15 8E CV5074 C tainment Ves el Vacuum Breaker 15 8F CV5075 Containment Vesse Vacuum Breaker 15 8G CV507 Containment Vessel uum Breaker 15 8H CVS 7 Containment Vessel Va m Breaker 15 8I 5078 Containment Vessel Vacuu Breaker 15  ; 8J CV5079 Containment Vessel Vacuum eaker 15 12 CC1567A Control Rod Drive Cooling Sup ly Line 15 12 CC1567B Control Rod Drive Cooling Supply Line 15 13 DR2012A Containment Vessel Normal Sump Drain 15 13 DR2012B Containment Vessel Normal Sump Drain 15 14 MU3 RCS Letdown Line 1 14 MU2A RCS Letdown Line 15

      .               1 DAVIS-BESSE, UNIT 1                     3/4 6-16
  ' )(   .

Nocket Number 50-346-

   'I) , Lice'nse Number NPF-3 R
        = Serial Number 1737                       TABLE 3.6-2 P

Attachment 1 Page'9- CONTAINMENT ISOLATION VALVES (0:: innd)- 3E.LETE) PENETRATION- VALVE NUMBER ISOLATIONf NUMBER FUNCTION TIME // r (secon )

                                                                                     /

16' RC1719A Containment' Vessel Vent Header- 10  ! 16 RC1719B Containment Vessel Vent Header 10 i 18 # SS598 Steam Generator Secondary V er ] Sample Line 10 l l 21 DV6831A De neralize ater Supply Line 10 i 21 DV6831B Dominer zed Vater Supply-Line 10 30 # B9A Containment Sump Emergency ecirc Line 71 31 # DH9B Containment Sump Emergency Recire Line 71 32 RC1773A RCS Drain to RC Drain Tank '0 32 RC1773B RCS Drain to RC Drain Tank 10 ' l l l l DAVIS-BESSE, UNIT 1 3/4 6-17 Amendment No. 3,72,112,114, 127

o j

           '.'     DockuS Number 50-346                                                                        l License Number NPF-3                                                                        1 Serial Number 1737                         TABLE 3.6-2                                    l Attachment 1 Page 10                      CONTAINMElff ISOLATION VALVES 'Crr*f ::d).

3 tile 7Ed i PENETRATION VALVE ISOLATION / NUMBER NUMBER FUNCTION TIME / (secon ) 41 RC232 Pressuriser Quench Tank Circulating Inlet Line 10 42A SA2010 Service Air Supply Line 10 I 42B CV5010E Containment Vessel Air Sample Peturn 15 l 43A IA2011 Instrument Air Supply Line 10 43B CV5011E containment Vessel Air sa le Return 15 44A C 5541 Core Flood Tank Fill a N2 Supply

Line 10 448 NN236 Pressurizer Quench ank N2 Supply Line 10 47A CT1545 reFloodTa!SampleLine 10 47B CP1542 Cor Flood Vent Line 10 48 RC229A Prest iser Quench Tank Circulating Outlet ne 10 i 48 RC2298 Pres rize- Quench Tank circulating L Out et Line 10 i

\ - 51 CV5037 Hydrogen Purge S tein Exhaust Line 60 , 51 CV5038 Hydrogen Purge Syst Exhaust Line 60 52 MU A Reactor Coolant Pump 1 Supply 12 53 66B Reactor Coolant Pump See Supply 12 54 MU66C Reactor Coolant Pump Seal S ply 12 55 MU6t>D Reactor Coolant Pump Seal Suppi 12 56 MU38 Reactor Coolant Pump Seal Return 12 MU59A Reactor Coolant Pump Seal Return 30 56 MU59B Reactor Coolant Pump Seal Return 30 56 MU59C Reactor Coolant Pump Seal Return 56 MU59D Reactor Coolant Pump Seal Return 30 I DAVIS-BESSE, UNIT 1 3/4 6-18 Amendment No. 79,109,114, 127 1 {.

ADDill0NAL htANGES PR[yl00 sty Docket Nur..b r 50-346 5 Licch:3 Number NPF-3 IN0POS[D BY LUTER *

     ' Serial Number 1737                            TABLE 3.6-2        a % _ N. N        DatL(hiff 7 Attachment 1 Page 11'                    C0fffAINMENT ISOLATION VALVES 'C:::in;;n.

ALETED PENETRATION VALVE NUMBER ISOLATION 7 NUMBER PUNCTION TIKE / ' (seconoi) 67 CV5090 Hydrogen Dilution Systen Supply 60 68A $5235^ Pressurizer Quench Tank Sample 30 SS235B Pressuriser Quench Tank Sample 30 685 CV5010B Containment Air Sample 15 68B CV5011B Containment Air Sample 15 69 CV5065 Hydrogen Dilution System Su ly 60 71B CV5010A Containment Air Saaple 15 71B C '011A Containment Air Sample 15 71C CP15 4 Core Flood Tank N2 P 1 10 73B CV501 Containment Air Sa le 15 73B CV5011C Containment Air ample 15 74B CV5010D ntainment A sample 15 74B CV5011D Cort ainment ir Sample 15 B. CONTAINMENT PURGE AND EXRAU ISOLATION 33 #9 CV5005 Co ainment 'essel Purge Inlet Line 10 , 33 ## CV5006 ontainment Ve sel Purge Inlet Line 10 34 ## CV5007 ContainmentVess(PurgeOutletLine 10 34 ## CV500 Containment Vessel urge Outlet Line 10 C. OTHER 5# SV1366 Containment Air Cooling Unit SV Inlet Line gf4 64 SV1368 Containeent Air Cooling Units SV Inlet Line N/A 7# SV1367 Containment Air Cooling Units SV Inlet Line N/A 9# SV1356 Containment Air Cooling Units SV Outlet Line g/A DAVIS-BESSE, UNIT 1 3/4 6-19 Amendment No. 31.75,127

                ' locket Number 50-346
           .,   License Number KPT-3
              - Serial Nuraber 1737                                TABM 3.6-2 Attachment 1 Page 12                          CONTAINMENT ISOLATION VALVES M r & x M l

3E LETEh ? PENETRATION VALVE ISOLATI0 NUMBER NUMBER TUNCTION TIME (seco s) 10 # SV1358 Containment Air Cooling Units SV Outlet Line N/A 1# SV1357 Containment Air Cooling Units SV i Outlet Line N/A 17 CV343 Containment Vessel Leak Test I et Line N/A 17 Flange Containment Vessel Leak Tes Inlet Line (Inside Containment) N/A 19 b6422 Normal RCS Hakeup Line N/A 19 # HP37 High Pressure Injecti Line N/A 19 # HP2A High Pressure Injec ion Line N/A 20 # HP56 High Pressure In etion Line N/A

                         .        20 #            HP2B       Uigh Pressure       jection Line                  N/A 22 #            HP49          gh Pressur Injection Line                      N/A 22 #           HP2D       His Press e Injection Line                        N/A 23 #           SF1        Fuel      sfer Tube                                N/A 23             Flange     Fuel T     for Tube                                N/A 24 #           ST2        Tue    ran er Tube                                 N/A 24             Flange     F 1 Transfe Tube                                   N/A
                                 *25              CS33         ontainment Sp y Line                             N/A
                                 *25              CS17       Containment Spr       Line                         N/A 25              SA536     Containment Spray         e                        N/A 25              SA5 2      Containment Spray Lin                             N/A
                                                     /

25 C51531 Containment Spray Line N/A 26 CS1530 Containment Spray Line N/A

                                 *26               CS36       Containment Spray Line                            N/A
                                  *26              CS18       Containment Spray Line                            N/A 26             SA535      Containment Spray Line                            N/A 2,             SA533      Containment Spray Line                            N/A 27 #           DH1A       Lov Pressure Injection Line                        N/A 27 #           DB76       Lov Pressure Injection Line                        N/A 28 #           DH1B       Lov Pressure Injection Line                         /A 28 #           DB77       Lov Pressure Injection Line                        N/A DAVIS-BESSE, UNIT 1                            3/4 6-20            Amendment No. 3, 112, 127

f preket Number 50-346

     -License Number NPF-3 Serial Number 1737 Attachment 1                                                       TASLR 3.6-2 Page 13 CO R AINNENT ISOLATION VALYtl- E: P d 1 6.LETE.TJ F NrrR&fran                       VALV NUNSER                            g            g                                                                    IS0ufroNf TINS /

(see )

                                *29 9                 DR11         Decay Seat Fump Suetica Line                                                 N/A
                                *29                   DB23         Decay Seat Fump Suetion Line                                                 N/A 99              FSV4849      Decay Seat Fump Secties Line                                                 N/A

! 35 AFS99 Auxiliary Feedvetor Line N/A , 36 9 AF608 Auxiliary Feedveter Lisa N/A 37 0 FW601 Main Feedvater Line N/A 38 9 FW612 Main Feedvetor Line N/A

                            **39 0                    N 00         Maia Steam Line                                                              N/A     '
                             **39 9                   ICS 4A       Nata Steen Line                                                              N/A 39 0               MS375        Maia Steen Line                                                              N/A .

39 9 NS100-1 Main Steen Li N/A

                               *39 9                  NS107           in Steen                                                                  N/A
                               *39 9                  NB107A           a Steep Line                                                             N/A     i I
                               *40 0                  NS106        Maik Stee's Line                                                             N/A
                               *40 t                  NS106A       Maia      'een Line                                                          N/A
                            **40 0                    N8101        Na     St         Line                                                       N/A
                            **40 t                    ICS118          la Steam           ao                                                     N/A   l 40 0                N8394           la Steen           y                                                      N/A s

40 t NS101- N/A 41 RC113Main ) SteamQueneb Fressuriser Lias \ Tank Inlet Line N/A , 41A SAM 2 Service Air Supply ne N/A 428 124 Centsiassat Vessel Ai Sample Retura N/A 43A IA501 Service Air Supply Line N/A , 438 CV115 containment Vessel Air e - Retura N/A 444 CF13 Core Flood Tank Fill and Nitro

                                    /                              Supply Line                                                                  N/A 8             1815 8       Fressuriser Quench Tank Inlet Line                                           N/A
                               *47A                   CF2A         Core Flood Tank Sample Line                                                  N/A l
                               *47A                   CF28         Core Flood Tank Sample Line                                                  M/A
                               *478                   CFSA         Core Flood Tank Vent Line                                                    N/

1 *478 CFSS Core Flood Tank Vent Line N/A

                                                                ~

ADDlil0NAL CHANCES PREV 100 sty PROPOSED LiY LETTER Serial No._E4] Date N3lA DAVIS-SSSSE, UNIT 1 3/4 6-21 Amendaset No. 3,114, 127 l

ADDITIONAL CHANGES PREVIOUSLY

         ' Docket Number 50-346
     . License Number NPT-3                                                      PROPOSED BY lilIER SeriM No. I'//5
       ' Serial Number 1737                                                                       Date sh//f7 i

Attachment 1 Page 14 TASLR 3.6-2 i CONTAINNENT ISOL4 TION VALVES CzirO g g PENETRATION VALYg ISOLATION NUMSER ggg yUNCTION ' TINB (sesemas) 49 DB87 Refueltag Canal Fill Line N/A DSB8 Refueling Canal Pill Line N/6

                                                                                                   /

50 RP48 Righ Pressure Injection Line 4/A 50 9 RP2C. Righ Pressure lajection Line N/A 50 NU6411 RCS Nakeup Line N/A 52 NU242 RCP Seal Vater Supply N/A 53 43 RCP Seal Water Supply N/A 54 44 RCP Seal Vater Supply N/A SS MU2 ACP Seal Vater Supply N/A, . 59 Plange Secondary Side Cleanlag Inside Containeest) / N/A 59 Flange Secondary Side Cleaping (Outside tainment) , N/A 57 9 M8603 5 Generat Blowdova Line M/A 60 6 MS611 St Geners Slowdown Line N/A 67 CV209 BydrogenN luttoa System Supply N/A 69 CV210 esV ution System Supply N/A Bydrog/ 71A 4 CY20008 Contpiamaat sessure Senser N/A 71C CP16 Ceraf Plood T itrogen Pill L$ae N/A 72A 9 CV20018 tainment Presso Sensor N/A 72C 6 CV6248 Containment Pressure afferential Transmitter N/A 73A 9 CV20024 Containment Pressure 'ser N/A 73C 9 CV6458' containment Pressure Diff eatial

                                             /        Transmitter                                  N/A 74A 9          CV20038      Containment Pressure Sensor                  N/A
                        *74C             p82735       Pressuriser Auxiliary Spray                  N/A
                        *74C                 736      Pressuriser Auxiliary Spray                  N/A
                          *May       ~ pened on an intermittent basis under administrativ control.

6Ho ubject to Type C leakage tests.

                       **S     veillance testing not required prior to entering N0DE 4 but sha 1 be forformedpriortoenteringMODE3.

6tProvisions of Specificatlon 3.0.4 are not applicable provided the valve is in the closed position and deactivated. D4VIS-SESSR, UNIT 1 3/4 6-22 Amendment No. 3, 31, M. 111,114.111. ; 135

i irocketNumber50-346 ' License Number HPF-3 Serial Number 1737 Attachment 1 Page 15 , CONTAINMDrr SYSTEMS 6 BASES [ leakage rate are consistent with the assumptions used in the safety analyses.  : The leak rate' surveillance requirements assure that the leakage assumed for the-systen during the recirculation phase vill not be exceeded. 3/4.6.2.2 ColfrAINNENT COOLING SYSTEN The OPERAh!LITY of the containment cooling systen ensures that 1) the containment air temperature vill be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions. 3/4.6.3 CONTAINNENT ISOLATION VALVES

                                  -                                 ~~%m                                    v __          . __ m The OPERABILITY of the containment isolation valves ensures that the containmen'tf
  • atmosphere vill be isolated from the outside environment in the event of a I release of radioactive material to the containment atipepp" herg or pressurisation
                            \       of the containment. Containment isolation within the4Yime" limits specified ,-

ensures that the release of radioactive material to the environment vill be (

                             ) consistent with the assumptions used in the analyses for a LOCA. GnhimnT
                           /         15olcdich WWes o.ad %r ce ned 15ohbd 6d am oddrewd A W                                                    .

06Af. . The cpenin j nn lokcmibd bu}'.s durmccfa. 1 cjos4d imperchk. Cadainned isoleck rcdien g pero 4Ned oder de>bblig > l Cedrel. O(kndM3 fm tdcdcp[y 7ao %se vaWes whM beepd

                       /

l uhder adhdnt$lrodivtcedrol cts well as 4hc so[c/gccCaubrM W)nclg / 1254 hc Men den qcaing Vah/es under such Cnf rels,,e' x

                                    ~~_..s.__._                                                                    _...-

1 DAVIS-BESSE, UNIT 1 B 3/4 6-3 Amendment No.135 l

yr -

 !      N Dock;t Number 50-346 g     Lic:ns] Nu:ber NPF-3
      . Serial Number 1737
 !        Attachment 2 I         Page 1 SIGNIFICANT HAZARDS CONSIDERATION Description of Proposed Technical Specification Change The purpose of this significant hazards consideration is to review proposed changes to Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1 Operating License,. Appendix A Technical Specifications (TS) 3/4.6.3.1, Containment Isolation Valves, Table 3.6-2, containment Isolation Valves, TS 3/4.6.1.1, Containment Integrity, TS Definition 1.8, Containment Integrity, and TS Bases 3/4.6.3, Containment Isolation Valves. This request proposes to remove TS Table 3.6-2 from the TS and relocate the list of containment isolation valves and associated information to the Updated Safety Analysis Report (USAR). This thange vould allow changes to be made to the table in accordance with 10CFR50.59 vhile maintaining the surveillance test requirements for containment isolation valves in the TS. In addition, several administrative        -j' changes have been made for clarification purposes. The Technical Description (Attachment 1) discusses these changes.

Significant Hazards Consideration The Nuclear Regulatory Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazard exists. A proposed amendment to an Operating License for a facility involves no significant hazards if operation of the facility in accordance with the proposed changes vould not 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of a new or different kind of an accident from any accident previously evaluated; or 3) Involve a significant reduction in a margin of safety. The proposed changes do not involve a significant hazards consideration because the operation of the Davis-Besse Nuclear Power Station, Unit Number 1, ' in accordance with these changes vould:

1. Not involve a significant increase in the probability or consequences of an accident previously evaluated because the relocation of the information in the Technical Specification Table to another controlled document is an administrative change which does not affect accident conditions and assumptions since no hardware changes are being made. [10CFR50.92(c)(1)]
2. Not create the possibility of a new or different kind of accident from any accident previously evaluated because the accident conditions and assumptions are not affected and no new initiators are created since the changes are administrative only and no hardware changes are being made. On matters related to nuclear safety, no new malfunctions are involved. [10CFR50.92(c)(2)]
3. Not involve a significant reduction in a margin of safety because the TS vill continue to require operable conteinment isolation valves and appropriate surveillance requirements to ensure operability of containment isolation. [10CFR50.92(c)(3)]

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                                  .'t: Decket Number.50-346 L.: 6J                               iLicen o Number.NPF-3'.                                                                    .
      /l*. ..
                                               . Serial Number'1737e ~                                                                     !

f '* , ) Attachment'2 i r ,- Page 2-'

   '                  ,*.-                                                                                                                i Conclusion'                                                                             .

Based on the discussion above, it is concluded tha_t the proposed changes do  ! p- not: involve a significant hazards consideration, j i

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