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{{#Wiki_filter:ATTACHMENT 2ATOAEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES'ARKEDTOSHOWPROPOSEDCHANGESUNIT1REVISEDPAGES3/40-33/43-2la3/44-383/44-403/47-153/49-13/49-135-65-7b6-49812080050 981203PDRADOCK05000815PPDR
{{#Wiki_filter:ATTACHMENT 2A TO AEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES
                    'ARKED  TO SHOW PROPOSED  CHANGES UNIT 1 REVISED PAGES 3/4  0-3 3/4  3-2la 3/4  4-38 3/4  4-40 3/4  7-15 3/4  9-1 3/4  9-13 5-6 5-7b 6-4 9812080050 981203 PDR  ADOCK 05000815 P              PDR
 
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34.0APPLICABILITY SURVEILLANCE REUIREMENTS b.Surveillance intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:
3 4. 0 APPLICABILITY SURVEILLANCE RE UIREMENTS
ASMEBoilerAndPressureVesselCodeandapplicable AddendaRequiredfrequencies forterminology forinservice performing inservice inspec-inspection andtestingcriteriationandtestingactivities WeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monthsYearlyorannuallyAtleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysc.Theprovisions ofSpecification
: b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME  Boiler  And Pressure  Vessel Code and    applicable Addenda          Required frequencies for terminology for inservice              performing inservice inspec-inspection and testing criteria tion and testing activities Weekly                    At least  once  per 7 days Monthly                  At least  once  per 31 days Quarterly or every 3 months            At least  once  per 92 days Semiannually or every 6 months        At least  once  per 184 days Yearly or annually                At least  once  per 366 days
: c. The provisions of Specification 4.0.2 are          applicable to the above required frequencies for performing          inservice inspection and testing activities.
: d. Performance    of the  above  inservice inspection and testing activities shall    be  in addition to other specified Surveillance Requirements.
e., Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
4.0.6          endments $ 00, 107 and 108 granted extensions        or cer a n su eillanck require to be p rformed n or before July 31, 1987, and    til  the end of e Cycle -10 refu ling outage.              or these speci c surve lances          der thi section, the sP cified ime interva requir d by Spe ificatio 4.0.2 w the new  i                                          ll be    termin d with tiation date es blished y the s eilla ce date during the Unit    1  987  refuelin outa e.
4.0.7          en  e                  e                    ann surveys  anc to be perfo      ed on o  before pril 1, 1989, until the end of the Cyc    10-11      fueling utage. For th e speci c su eillan es under this ext sion, t p speci ed          ti    interv s req ired b Specifi ation 4. 2 will bq dete ned wx h the n q ini ation te establis d by the urveillance date durin the Un' 1 89 refueling 'out COOK NUCLEAR PLANT -      UNIT 1            3/4 0-3              AMENDMENT NO.ggg <</gal <<144
 
3/4        LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3      INSTRUMENTATION TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF      CHANNELS        CHANNELS    APPLICABLE FUNCTIONAL UNIT                CHANNELS          TO TRIP          OPERABLE      MODES      ACTION
: 6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
: a. Steam Generator        3/Stm. Gen.        2/Stm. Gen.      2/Stm. Gen.      1,2,3      14 Water Level-Low-                          any Stm.Gen.
Low
: b. 4 kv Bus Loss  of      3/Bus              2/Bus          , 2/Bus            1,2,3    14 Voltage Pump Start                                2/bus  (Tl I A-Train B; T11D-Train A)
Valve Actuation (Both                    2/bus on trains)                                  (Tl IA 8c T11B or 2/busses Tl lc &
T11D)
: c. Safety Injection                                                              1, 2, 3    18
: d. Loss of Main                                                                    1,2      18 Feedwater Pumps
: 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
: a. Steam Generator        3/Stm. Gen.        2/Stm. Gen.      2/Stm. Gen.      1, 2, 3    14 Water Level-Low-                          any 2 Stm.
Low                                      Gen.
: b. Reactor Coolant Pump 4-1/Bus                                                  1,2,3      19 Bus Undervoltage
: 8. LOSS OF POWER
: a. 4  kv Bus Loss of      3/Bus              2/Bus            2/Bus          1,2,3,4      14 Voltage
: b. 4 kv Bus Degraded        3/Bus              2/Bus            2/Bus          I, 2, 3,  4  14 Voltage              (Ttl 8 TraInlj      (Ttth-TrRI'~Sj (rttA-7~:~8>
at t) - Tr~'~h)      Yttb-frai~h)      sub-T~t~h)
COOK NUCLEAR PLANT-UNIT 1                        Page 3/4 3-21a                    AMENDMENT$ C,  ~, 153
 
4.4.$ 2.1  Both Reactor Vessel head vent paths    shall be deaanstrated  OPI',RAB least once per 18 months by:
: 1. Verifying the ccmaaa manual isolation valve in the Reactor vessel head vent  is sealed in the open position.
: 2. Cycling each of the remotely operated valves in esoh path through at least one complete cycle of full travel tree the Control RocNa while in Bodes 5 or 6.
3~  Verifying floe through both of the Reactor Vessel    head  vent paths dur ing vaat~ operation, awhile in Bodes 5 or 6.
AeQ.lance equiraaen      to demons ate the oper ility of eac eactor V el head ve        path vQ,l e performed he next time e unit enters H ES 5 or 6 spec1r1 tion, and Ilying th issuance of his Technical or the app prtate pl      prccednrea      ee been vritten.                                                        p D. C  COOK  -  UNIT  l                    3/4 4-38
 
4.4.$ g.2 Both        suriser s~eaa space veat paths shall      be deneastrated 0?          at least oace pec 18 cenths byc
: f. Verifying the    comma aaaual      isolation valvo ia the Pressurizer st04$ space vent    is sealed ia the open yoaitioao Cyoliag each    of the reaetely operated valves in each yath through at least  oae  ooaplete cycle of full travel froa tho Coatrol Rooe
                ~e      in  Hades 5  or 6.
: 3. Verifying flam through both of the Pressurizer steaa sycLce rent yaths 4uriag veatiag operation,        ~le  in }fedos 5 oc'.
illanoe req urer ants      to  4    nstrate t ~ operabi    y of each Pr            ste    space veat      th Wll b perfo        the next t    the t eaters      ES 5 oc'    f    loviag the ssuaaoe      this Techaiy after                  te Plant rocedures hag@ been e'it tea.  /
Speed.fkcati9,    aad            e appropr D ~ C o COOK 3/4 4-40                        Aaaadmeat ceo.98
 
C OOL  G V TE 0  0 ERATIO 3.7.3.1
: a. At least two independent component cooling water loops shall be OPERABLE.
ML
: b. At least wnce component cooling water flowpath in support of Unit      2 shutdown functions shall be available.
Specification 3.7.3.1.b - At      all times when Unit 2 is in MODES  1, 2, 3, or 4.
~CT~IO V&bh  Specification 3.7.3.1.a is applicable:
Vith only    one component    cooling water loop OPERABLE, restore at least two loops to OPERABLE  status within    72 hours or be in at least HOT STANDBY within the next 6 hours and in    COLD  SHUTDOWN within the following 30 hours.
When  Specification 3.7.3.1.b is applicable:
With no flowpath to Unit 2 available, 'return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12,hours and HOT SHUTDOWN .within the following 24 hours. The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.3.1    At least two component cooling .water loops shall be demonstrated OPERABLE'.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.
: b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety In]ection test signal.
: c. By  verifying  pump  performance pursuant to Specification 4.0.5.
: d. At least once per 18 months during shutdown, by verifying that thehcross-tie valves can cycle full travel. Pollowing cycling, the valves will be verified to be in their closed positions.
COOK NUCLEAR PLANT    - UNIT  1            3/4 7-15      AMENDMENT NO. 447, 434, 444, 164
 
rI I
 
G  0 ORO    CONCE LIMITING CONDITION        FOR OPERATION 3.9.1 With the reactor vessel head unbol'ted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
: a.      Either  a K
                          .eff  of 0.95 or less, which includes ffallowance                            a 1%  Jc/k conservative                for uncertainties, or
: b. A  boron concentration of greater than or equal to 2400 ppm, which includes    a 50 ppm conservative allowance for uncertainties.
~CT~O With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes~+ and initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or its equivalent until Keff            f is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.
SURVEILLPSCE RE UIREMENTS 4.9.1.1    The more    restrictive of the      above two reactivity conditions shall    'oe determined    prior to:
: a. Removing or      unbolting the reactor vessel head, and
: b. Withdrawal of any        full length  control rod in excess of    3 feet from
            'its fully inserted position.
4.9.1.2    The boron    concentration    of, the reactor coolant  system and the
~~~it~Mxi                                                          72 hours.
0ACe. pe,r
* The  reactor shall      be  maintained in  MODE 6 when the reactor vessel head is unbolted or removed.
*~ For purposes      of this specification, addition of water from the RWST does not constitute      a  positive reactivity addition provided the boron concentration in the  RWST  is greater than the minimum required by Specification 3.1.2.7.b.2.
D. C. COOK - UNIT 1                          3/4 9-1                    AMENDMENT NO.
 
~
      ~
c'          ~l 3,9.12              The  spent fuel storage pool exhaust    ventilation    system  shall  be OPERABLE.
Whenever  irradiated fuel is in the storage pool.
a ~      With no fuel storage pool exhaust yentilati.on system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*
: b.        The  provisions of Specificati'ons 3.0.3 and 3.0.4 are not applicable.
                  '4C 4.9.12            The above    required fuel storage pool ventilation system shall          be demonstraied t          OPERABLE:
: a.        At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.
At least once per 18 months or (1) after any structural. maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
: 1. Deleted.
: 2. Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm +    10%.
oor y  e ovxfli(h lovi14n  c~(aN8 ~+7 5ov
* The crane bay roll-up door and the runua&g-room-rcrH~~oer may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool,
~      Shared system with D. C. COOK - UNIT 2.
This does not include the main load block. For purposes of this specification, a deenergi"ed main load block need not be considered a load.
D. C. COOK - UNIT 1
        ~                                            3/4 9-13        Amendment No.      1~4
 
I 5.0    DESIGN FEATURES 5.6 FUELSTORA E Continued Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.
: 2.      Region 2 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
: 3.      Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
                                                      ~
The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations,'nt+raphicalbpdepieted-i~re-5 Minimum Assembly Average Burnup in MWD/MTU =
                                          - 22,670 + 22,220 E - 2,260 E + 149      E3 Minimum Assembly Average Burnup in MWD/MTU =
                                          - 26,745 + 18,746 E - 1,631 E + 98.4      E3 Where E    = Initial Peak Enrichment 5.6.1.2:      Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:
Maximum Nominal Fuel Assembly Enrichment Description                                                  Wt. % U-235
: 1)      Westinghouse                  15 x 15 STD                        4.95 15 x 15 OFA
: 2)      Exxon/ANF                    15 x 15                            4.95
: 3) . Westinghouse                  17 x 17 STD                      '.95 17 x 17 OFA 17 x 17 V5
: 4)      Exxon/ANF                    17 x 17                            4.95 COOK NUCLEAR PLANT-UNIT 1                          Page 5-6            AMENDMENTSV, 436, 4N, 44&, 213
 
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l OO        2.0                          ~      S.O
                        !NGl4. - IRIPIMEHT. aU-235 CWGK i'~
 
6.0      ADMINISTRATIVECONTROLS
        *'' *""Q*''*'"
6.3.1    Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must holMr-htt~eld-a-Senier-Operatm-license as specified in Section 6.2.2P..
6.4 TRAINING                              e    t;<;t. 4 va.tig) 6.4.1    A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements        and recommendations  of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
5.5 REVIEW AND AUDIT 6.5.1  PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1            The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.
COMPOSITION 6.5.1.2            The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited tn Operations, Technical Support, Licensing, Maintenance and Radiation Protection The PNSRC membership shall consist of at least one individual from each of the areas designated.
All members, including the Chairman and his ahemates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
COOK NUCLEAR PLANT-UNIT 1                              Page  64                  AMENDMENT49,        4B) 48K, 454) 486)  4Q) 212
 
ATTACHMENT 2B TO AEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES MARKED TO SHOW PROPOSED CHANGES UNIT 2 REVISED PAGES 3/4 0-3 3/4 0-4 3/4 3-11 3/4 3-20 3/4 3-30 3/4 3-31 3/4 3-34 3/4 3-44d 3/4 3-47 3/4 4-13 3/4 4-14 3/4 4-33 3/4 4-35 3/4 4-37 3/4 5-4 3/4 5"8 3/4 6-12 3/4 6-14 3/4 6-47 3/4 7-12 3/4 7-13 3/4 7-16a 3/4 7-20 3/4 8-9 3/4 8-13 3/4 8-15 3/4 9"12 5-6 5-8 6-4
 
3 4A  APPLICABILITY SURVEILIANCE RE UIEUUKNTS
: b. Surveillance Intervals specified in Section XI of the ASME Boiler    and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities xequired'y the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follow's ia these Technical Specifications:
ASME    Boiler  And Pressure Vessel Code and      applicable-Addenda              Required frequencies    for terminology for inservice                    performing inservice inspec-ins ection and testin          criteria      tion  and  testin activities Weekly                    At  least  once  per 7 days Monthly                  At  least  once  per 31 days
                      ~rterly or every 3 months              At  least  once  per 92 days Semiannually or every 6 months      , At  least  once  per 184 days Yearly or annually                  At  least  once  per 366 days
'o      d.
The provisions of Specification 4.0.2 axe applicable to the above
              'required frequencies for performing insexvice inspection and testing activities.
Performance mctivities shall of the be above  inservice inspection and testing in addition to other specified Surveillance Requirements.
e~  Nothing in the ASME Boiler and Pressure Vessel Code shall be con-stxued to supersede the requirements of any Technical Specification.
                'ba, 4.0.6          en            g an e e ens ons or cer          n surve    ances required to    be per ormed gn or bef re Mar h 31, 1 86, unti the end of the Cyc~ e 5-6      efueliilg outage    For'se    sp cific s      eillanc) under this ectio the s$ cified time in exvals equired y Speci catio 4.0.2      ill  be determi ed with the ne b the urveil ance da e durin the Unit 2 1984 refu nitia )on date establis ed outa e.
4.0.7      Amendments 97 and 99        granted extensions for certa n re uired to        e perform d on or be re July~1, 1988, until the end of th Cycle 6- refueling utage. Fo these h ecific s eillan es unde this sec on, the s ecified t e inte                  ls requir d by Speci cation 4. .2 will be determine with th new init ation                      te establi +ed by the surveilla ce date d ng the outage.
it 2 19    refueling COOK NUCLEAR PLANT      - UNIT 2              3/4 0-3            AMENDMENT NO. 7 g, g7, 1 31
 
1
  't
    )
 
3 40    LXC SURVEILLANCE 4.0.8      By specific re erence to          s sect on,      ose surve    ances which must be p rformed on or before hu
                -month r 36-mo t 13, 1994, and are designed as surve lances or re          ed as ou ge-related s    eillan s unde the pro sions o Specifi ation 4..5) may be del ed unt the en of the cl'e 9-10 efueli outage. For these spec ic s        eillanc s under this se tion,              speci ied time inte ls re red by pecifica ion 4.0. will b determ ed with the ne initiat on date stablish d by the surveill ce dat during th'e Unit 2 1994 efuelin outa e.
4.0.9      By  specific re erence to        s sect on,      ose surve    ances whi.ch mus    be performed on      before  eptemb  r 7,  19 4, and a    desi  ted as 1 month      h~eillan    es may    e dela  d  unti just pr or to      re eload    n the tJqit 2 Cy  e 9-10    efueli    outa COOK NUCLEAR PLANT    - UNIT 2          3/4 0-4                      AMENDMENT NO.  ~,  166
 
T B.E    3-n O                                  CTOR I  SYST  ST  E      0      S    V  C      U CHANNEL        MODES  IN WllICH CHANNEL        CHANNEL                FUNCTIONAL        SURVEILLANCE FUNCTIONAL UNI                          ~GEE        C              0        ~AT.                  R  U R
: 1. Manual Reactor Trip A. Shunt Trip Function                N.A.            N.A.            ~
S/U(1) (10)              3*, 4*, 5*
B. Undervoltage Trip                N.A.            N.A.                S/U(1) (10)              3*, 4*, 5*
Function
: 2. Power Range,  Neutron Flux                        (20 ) IM(      I )    M  and  S/U(l)  1, 2 and
* and Q(608)
: 3. Power Range, Neutron    Flux,          N.A.            R(6)                                1,  2 High Positive Rate
: 4. Power Range,  Neutron Flux,          N.A.            R(6)                                1, 2 High Negative Rate
: 5. Intermediate Range,                                          '(6,8)
S/U(l)          1,  2 and
* Neutron Flux
: 6. Source Range, Neutron Flux                            R(6,14)            M(14) and S/U(l) 2(7), 3(7),
4 and 5
: 7. Overtemperature  AT                                  R(9)g                                1,  2 a
W
: 8. Overpower  AT                                        R(9)e"                              1, 2
: 9. Pressurizer Pressure--Low                              Re                                  1, 2 o
: 10. Pressurizer  Pressure--High                          RP                                  1, 2
                                                                                                    ~
ll. Pressurizer  Water Level--High                        aQ                                  1,  2
: 12. Loss  of Flow - Single Loop                            R(8)


==4.0. 2areapplicable==
r>
totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.
t 0
d.Performance oftheaboveinservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.
e.,NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.
4.0.6endments$00,107and108grantedextensions orceransueillanckrequiretobeprformednorbeforeJuly31,1987,andtiltheendofeCycle-10refulingoutage.orthesespecicsurvelancesderthisection,thesPcifiedimeintervarequirdbySpeificatio4.0.2wllbetermindwiththenewitiationdateesblishedytheseillacedateduringtheUnit1987refuelinoutae.4.0.7eneeannsurveysanctobeperfoedonobeforepril1,1989,untiltheendoftheCyc10-11fuelingutage.Forthespecicsueillanesunderthisextsion,tpspeciedtiintervsreqiredbSpecifiation4.2willbqdetenedwxhthenqiniationestablisdbytheurveillance datedurintheUn'189refueling
'outteCOOKNUCLEARPLANT-UNIT13/40-3AMENDMENT NO.ggg<</gal<<144 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.3-3Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT6.MOTORDRIVENAUXILIARY FEEDWATER PUMPSMINIMUMTOTALNO.OFCHANNELSCHANNELSAPPLICABLE CHANNELSTOTRIPOPERABLEMODESACTIONa.SteamGenerator WaterLevel-Low-Low3/Stm.Gen.2/Stm.Gen.2/Stm.Gen.anyStm.Gen.1,2,314b.4kvBusLossofVoltagePumpStartValveActuation (Bothtrains)c.SafetyInjection d.LossofMainFeedwater Pumps7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPS3/Bus2/Bus2/bus(TlIA-TrainB;T11D-TrainA)2/buson(TlIA8cT11Bor2/bussesTllc&T11D),2/Bus1,2,31,2,31,2141818a.SteamGenerator 3/Stm.Gen.WaterLevel-Low-Lowb.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOFPOWERa.4kvBusLossof3/BusVoltage2/Stm.Gen.any2Stm.Gen.2/Bus2/Stm.Gen.2/Bus1,2,31,2,31,2,3,4141914b.4kvBusDegraded3/BusVoltage(Ttl8TraInljatt)-Tr~'~h)2/Bus2/BusI,2,3,4(Ttth-TrRI'~Sj (rttA-7~:~8>
Yttb-frai~h) sub-T~t~h) 14COOKNUCLEARPLANT-UNIT 1Page3/43-21aAMENDMENT
$C,~,153 4.4.$2.1BothReactorVesselheadventpathsshallbedeaanstrated OPI',RABleastonceper18monthsby:1.Verifying theccmaaamanualisolation valveintheReactorvesselheadventissealedintheopenposition.
2.CyclingeachoftheremotelyoperatedvalvesinesohpaththroughatleastonecompletecycleoffulltraveltreetheControlRocNawhileinBodes5or6.3~Verifying floethroughbothoftheReactorVesselheadventpathsduringvaat~operation, awhileinBodes5or6.AeQ.lance equiraaen todemonsatetheoperilityofeaceactorVelheadvepathvQ,leperformed henexttimeeunitentersHES5or6IlyingthissuanceofhisTechnical spec1r1tion,andortheappprtateplprccednrea peebeenvritten.D.CCOOK-UNITl3/44-38 4.4.$g.2Bothsurisers~eaaspaceveatpathsshallbedeneastrated 0?atleastoacepec18centhsbycf.Verifying thecommaaaaualisolation valvoiathePressurizer st04$spaceventissealediatheopenyoaitioao CyoliageachofthereaetelyoperatedvalvesineachyaththroughatleastoaeooapletecycleoffulltravelfroathoCoatrolRooe~einHades5or6.3.Verifying flamthroughbothofthePressurizer steaasycLcerentyaths4uriagveatiagoperation,
~lein}fedos5oc'.illanoereqantsto4nstratet~operabiyofeachPrurerstespaceveatthWllbperfothenextttheteatersES5oc'floviagthessuaaoethisTechaiySpeed.fkcati9, aadaftereapproprtePlantrocedures hag@beene'ittea./D~CoCOOK3/44-40Aaaadmeat ceo.98 C
3.7.3.1OOLGVTE00ERATIOa.Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.
MLb.Atleastwncecomponent coolingwaterflowpathinsupportofUnit2shutdownfunctions shallbeavailable.
Specification 3.7.3.1.b
-AtalltimeswhenUnit2isinMODES1,2,3,or4.~CT~IOV&bhSpecification 3.7.3.1.a isapplicable:
Vithonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.3.1.b isapplicable:
WithnoflowpathtoUnit2available,
'returnatleastoneflowpathtoavailable statuswithin7days,orprovideequivalent shutdowncapability inUnit2andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit2inHOTSTANDBYwithinthenext12,hoursandHOTSHUTDOWN.withinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent cooling.waterloopsshallbedemonstrated OPERABLE'.
Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequip-mentthatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyIn]ection testsignal.c.Byverifying pumpperformance pursuanttoSpecification 4.0.5.d.Atleastonceper18monthsduringshutdown, byverifying thatthehcross-tievalvescancyclefulltravel.Pollowing cycling,thevalveswillbeverifiedtobeintheirclosedpositions.
COOKNUCLEARPLANT-UNIT13/47-15AMENDMENT NO.447,434,444,164 rII G0OROCONCELIMITINGCONDITION FOROPERATION 3.9.1Withthereactorvesselheadunbol'ted orremoved,theboronconcentration ofallfilledportionsoftheReactorCoolantSystemandtherefueling canalshallbemaintained uniformandsufficient toensurethatthemorerestrictive ofthefollowing reactivity conditions ismet:a.EitheraKffof0.95orless,whichincludesa1%Jc/k.effconservative allowance foruncertainties, orb.Aboronconcentration ofgreaterthanorequalto2400ppm,whichincludesa50ppmconservative allowance foruncertainties.
~CT~OWiththerequirements oftheabovespecification notsatisfied, immediately suspendalloperations involving COREALTERATIONS orpositivereactivity changes~+
andinitiateandcontinueborationatgreaterthanorequalto10gpmof20,000ppmboricacidsolutionoritsequivalent untilKfisreducedefftolessthanorequalto0.95ortheboronconcentration isrestoredtogreaterthanorequalto2400ppm,whichever isthemorerestrictive.
Theprovisions ofSpecification 3.0.3arenotapplicable.
SURVEILLPSCE REUIREMENTS 4.9.1.1Themorerestrictive oftheabovetworeactivity conditions shall'oedetermined priorto:a.Removingorunbolting thereactorvesselhead,andb.Withdrawal ofanyfulllengthcontrolrodinexcessof3feetfrom'itsfullyinsertedposition.
4.9.1.2Theboronconcentration of,thereactorcoolantsystemandthe~~~it~Mxi72hours.0ACe.pe,r*Thereactorshallbemaintained inMODE6whenthereactorvesselheadisunboltedorremoved.*~Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.
D.C.COOK-UNIT13/49-1AMENDMENT NO.
~~c'~l3,9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.
Wheneverirradiated fuelisinthestoragepool.a~Withnofuelstoragepoolexhaustyentilati.on systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepooluntilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.*b.Theprovisions ofSpecificati'ons 3.0.3and3.0.4arenotapplicable.
'4C4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbetdemonstraied OPERABLE:
a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.Atleastonceper18monthsor(1)afteranystructural.
maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following
: painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove>99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfm+10%.5ovooryeovxfli(hlovi14nc~(aN8~+7*Thecranebayroll-updoorandtherunua&g-room-rcrH~~oer maybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool,~SharedsystemwithD.C.COOK-UNIT2.~~Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adeenergi"ed mainloadblockneednotbeconsidered aload.D.C.COOK-UNIT13/49-13Amendment No.1~4 I
5.0DESIGNFEATURES5.6FUELSTORA EContinued Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wt%U-235,orspentfuelregardless ofthedischarge fuelburnup.2.Region2isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast50,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.
3.Region3isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast38,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.
Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations,'nt+raphicalbpdepieted-i~re-5
~MinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,260E+149E3MinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2:Fuelstoredinthespentfuelstorageracksshallhaveamaximumnominalfuelassemblyenrichment asfollows:Description MaximumNominalFuelAssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3).Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.95'.954.95COOKNUCLEARPLANT-UNIT 1Page5-6AMENDMENT SV,436,4N,44&,213 egonsIrQXC4.Q~~~COO1>eeocIr~'CC'CCC::SCHMOCLIOOOOrrrSXOOOAc)I"-IoUR.P9QMiNIJH""OABLE3URN'DCM+Hl2.0~S.O!NGl4.-IRIPIMEHT.
aU-235CWGKi'~


==6.0 ADMINISTRATIVE==
TABLE    3.3-3  Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.        CHANNELS      CHANNELS      APPLICABLE FUNCTIONAL UNIT                    OF CHANNELS      TO TRIP        OPERABLE          MODES        ACTION
CONTROLS*''*""Q*''*'"
: 7. TURBINE DRIVEN AUXILIARYFEEDWATER          PUMPS fl t
6.3.1Eachmemberofthefacilitystaffshallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustholMr-htt~eld-a-Senier-Operatm-license asspecified inSection6.2.2P..eva.tig)t.46.4TRAININGt;<;6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.5.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.
: a. Steam Generator Water      3/Stm. Gen.      2/Stm.          2/Stm.        1, 2, 3          14*
Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtnOperations, Technical Support,Licensing, Maintenance andRadiation Protection ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.
Level--Low-Low                              Gen. any        Gen.
Allmembers,including theChairmanandhisahemates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.
2  Stm.Gen.
Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.
: b. Reactor Coolant            4-1/Bus                                        1, 2,  3        19*
COOKNUCLEARPLANT-UNIT 1Page64AMENDMENT 49,4B)48K,454)486)4Q)212 ATTACHMENT 2BTOAEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGESMARKEDTOSHOWPROPOSEDCHANGESUNIT2REVISEDPAGES3/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/40-30-43-113-203-303-313-343-44d3-474-134-144-334-354-375-45"86-126-146-477-127-137-16a7-208-98-138-159"125-65-86-4 34AAPPLICABILITY SURVEILIANCE REUIEUUKNTS b.Surveillance Intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities xequired'y theASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollow'siatheseTechnical Specifications:
Pump Bus Undervoltage
ASMEBoilerAndPressureVesselCodeandapplicable-Addenda terminology forinservice insectionandtestincriteriaRequiredfrequencies forperforming inservice inspec-tionandtestinactivities
: 8. LOSS OF POWER I
'od.WeeklyAtleastonceper7daysMonthlyAtleastonceper31days~rterlyorevery3monthsAtleastonceper92daysSemiannually orevery6months,Atleastonceper184daysYearlyorannuallyAtleastonceper366daysTheprovisions ofSpecification
: a. 4 kV Bus                    3/Bus            2/Bus          2/Bus        1, 2, 3, 4        14*
Loss  of Voltage
: b. 4 kV Bus Degraded          3/Bus            2/Bus          2/Bus        1, 2, 3, 4        14*
Voltage                (Qi A - (nfl'i      (T7lb TmlnBj (T2lA Tm'+Si 721 l) VIE+ Qj      Tz, I D- Twi<<)  T't< D-<~'<4) 9 ~  MANUAL
: a. Safety Injection (ECCS)      2/train        1/train        2/train      1, 2, 3, 4          18 Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
: b. Containment Spray            1/train        1/train        1/tra'in      1, 2, 3, 4          18 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation    Fan
: c. Containment      Isolation- 1/train          1/train        1/train        1, 2, 3, 4        18 Phase "A" Containment Purge and Exhaust Isolation
: d. Steam Line      Isolation    2/s team        2/s team      2/opera-      1, '2,  3            20 line  (1       line    (1    ting steam per train)      per            line (1 train)        per train)
COOK NUCLEAR      PIANT - UNIT 2                3/4 3-20                  AMENDMENT NO        g7 'j fgg ~
137
 
3/4 .. LIMI'HNGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3    INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS ACTUATING  MODES IN CfiANNEL    CHANNEL IEEI'RIP CHANNEL FUNCTIONAL DEVICE OPERATIONAL WHICH SURVEILLANCE FUNCTfONAL UNIT            CHECK    CALI RAIIDH                                      SQUIRED
: l. SAFETY INIECIION, TURBINE TRIP, FEEDWATER ISOLATION.
AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
: a. Manual Initiation                                  Scc Functional  Unit 9
: b. Automatic Actuation        N.A.      N.A.            M(2)               N.A.      I, 2, 3, 4 Logic
: c. Containm<<nt Pressure-                                  M(3)               N.A.        1,2,3 High
: d. Pressurixcr Prcssurc-                                                       N.A.        I, 2, 3 Low
: c. DifFerential Pressure                                                      N.A.        I, 2,  3 Bctwccn Steam Lines High
: f. Stcam Lue Pressure-                                                         N.A.        1,2,3 Low
: 2. CONTAINMENTSPRAY
: a. Manual Initiation                                  Sce Functional  Unit 9
: b. Automatic Actuation        N.A.       N.A.             M(2)               N.A.     1,  2, 3, 4 Logic
: c. Concunmcnt Pressure-                                    M(3)              N.A.       1,2,3 High.High
: 3. CONTAINMENT ISOLATION
: a. Phase  'A  Isolation I)  Manual                                        Scc Functional Unit 9
: 2)  From Safety            N.A.       N.A.             M(2)              N.A.     1, 2, 3, 4 Injection Automatic Actuation Logic
    '. Phase    B'solation I)  Manual                                        Scc Functional Unit 9
: 2)  Automatic Actuation    N.A.                       M(2)                N.A. 1,2,3,4 Logic
: 3)  Containmcnt              S                        M(3)                N.A.       1, 2', 3 Pressure- f{igh.
High COOK NUCLEAR PLANT-UNIT2                        Pago 3/4 3-30 AMENDMENT34, 434, 4K,     158
 
C J
 
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3    INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING  MODES IN CHANNEL              DEVICE    WHICH CHANNEL    CHANNEL      FUNCTIONAL        OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT            CHECK  CALIBRATION        TEST              TEST    ~RE UlRED l
: c. Purge and Exhaust Isolation I) Manual                                        Scc Functional Unit 9-
: 2)  Containment                                                          N.A. 1,2,3,4 Radioactivity High
: 4. STEAM LINE ISOLATION
: a. Manual                                          Sec Functional Unit 9
: b. Automatic Actuation        N.A.      N.A.            M(2)              N.A.      I, 2, 3 Logic
: c. Containmcnt Pressurc-                                  M(3)              N.A.     I, 2, 3 High-High
: d. Steam Flow in Two                                                        N.A.      I, 2, 3 Steam Lines  - High Coincident with T,,
Low-Low
: c. Steam  Linc'Prcssurc-                                                    N.A.      1,2,3 Low S. TURBINE TRIP AND FEEDWATER ISOLATION N.A.     1,2,3
: a. Steam Generator Water Level  High-High
: 6. MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
: a. Stcam Generator iVater                                                              I, 2, 3 Level  - Low-Low
: b. 4 kV Bus Loss    of                                                                I, 2, 3 Voltage
: c. Safety Injection          N.A.       N.A.             M(2)              N.A.     I, 2, 3
: d. Loss of Main Feed        N.A.      N.A.                                N.A.        1,2 Pumps
    "%teart)vhion~~tnicaLSpcciiieatiea-4A)A Ltpplicable.
COOK NUCLEAR PLANT-UNIT2                        Page 3/4 3-31            AMENDMENTaI,    &, 434,  434, 4W, 459, 16S
 
P k
0
 
3/4. 3.3 KOH~~OEIHC  GiSTM~LTION LXKKTZSC COHDZTZOS FOE QPKLLTIQS 3.3.3.1 Tahoe spec'~~
Tha r a~~~ mcraiarz~
3.~~4 ahaU. be QPKLL'.KZ    ~ ~ ~/~~~~mantas~mn      ~mn~
sespo~
ahcncn W~ the    )
CXEZLZZT:  ha  abc'      Tabb<  3.~.
                          ~~
JCXZOE:
: a. V'A a              non'~~      channel akaxa/a~
aespoins  czcaa~      tha vaLaa shee w Table 3.M, adgnos or  de~a
                            ~    aetpo~ to Mahdi tha Xfad.t tha channel fmoperabIa.
W~      4 boers bo    %~A one oT ncce    t~~~
ezabla, rake the    ~Hcelt?ftoT~
ebcnca ch@nL'e fa Tabl.a 3.~.
: c. The  pmvta~      of Spe~caeLana      3.0.3 cad 3.0.4 are not apylf cabLa.
4.3.3.1    Each  zmLfaahan    zoon" metal                      c1nnuaak  ahaLl be as she fx'eqnencMs abner    ia  TabLa 4.3 3.
~i~eh Q ca1
~H4ng-osage D, C. CQOK~      2                      3/4  3 34    A$EtldQolTC )f0 ~ 43
 
ri                                                        V  0    0    0    G O                                                  V          G      V    E  S O                                                          ~
ClhNNEL                  CllANNEL c< Xuasauumr: ir                                      &#xb9;LE~0                            ~CWCQ                  C          0 ri
: 1. Steam Generators and 4 Level 1                          41 Cabinet LSI Cabinet 4 l and 2,    Steam Generators  2                          LSI Cabinet 2 and and 3 Lovel                                  LSI Cabinet 4
: 3. Steam Generators  1                          LSI Cabinet 4 and and 4 Prossure                              LSI Cabinet 5 Steam Generators  2                          LSI Cabinet 4 and and 3 Pressure                              LSI Cabinet 6 5,    Reactor Coolant Loop                        LSI Cabinet 4 and 4 Temperature (Cold)                        LSI Cabinet 5
: 6. Reactor Coolant Loop                        LSI Cabinet 4 and                                              Ry  )
4 Temperature (llot)                        LSI Cabinet 5 7,    Reactor Coolant Loop                        LSI Cabinet 4 and 2 Temperature (Cold)                        LSI Cabinet 6 8.,  Roactor Coolant Loop                        LSI Cabinet 4 and 2 Temperature (llot)                        LSI Cabinet 6
: 9. Pressurizer Lovel  .                        LSI Cabinet  3 eg 0
10.
ll.
Raactor Coolant System Pressure Charging Cross-Flow Between Units Source Range Neutron Detector (N-23)
Kiev. 587'/a LSI Cabinet gorridor LSI Cabinet 4 3
n/a R'2.
* Cbarging Gross-1'low between Units is an instrpment common to'both    Unit 1 and 2,  Tbis surveillance vill only bo conducted on an interval consistent Mith Unit 1 refueling.
wu hl                                                      I
 
r>
BL    3- 0 OS  - C        Ol TORING  S    E  AT 0    0 V            U  E E CJNNHEL
                                                                ~CEEC
: 1. Containment Pressure                                          M Reactor Coolant Outlet Temperature - Tgp) (Hide Range) 2 3
  ~
  ~  Reactor coolant Inlet Temperature -           (Hide Range)
M                        R +
Reactor Coolant Pressure  Hide RangeT<<,p M
4,                                                                    M
: 5. Pressurizer Water Level                                        M
: 6. Steam Line Pressure                                            M                        R 7  ~  Steam Gei>orator Hater Level  Narrow Range                    M                        R
: 8. BHST Water Level                                              M                        R
: 9. Boric Acid Tank Solution Level                                M 10'1. Auxiliary Feedwater Flow Rate                                  M Reactor Coolant System Subcooling Margin Monitor              M 12  ~ PORV Position Indicator  Limit Switches                      M
: 13. PORV Block Valve Position Indicator  Limit Switches          M                        R
: 14. Safety Valve Position Indicator  Acoustic Monitor            M                        R
: 15. Incore Thermocouples (Core Exit Thermocouples)                M
: 16. Reactor Coolant Inventory Tracking System                      M(2)                    R(1)%'(3)P (Reactor Vessel Level Indication) 17  ~ Containment Sump Level                                        M                        R 1B. Containment Hater Level                                        M Partial  range channel  calibration for sensor to    be performed below P-12    in MODE  3.
(2) Hith one      train of Reactor    Vessel Level Indication inoperable, Subcooling Margin Indication  and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.
(3)    Completion of channel cal'ibration for sensors to be. performed below P-12 in MODE 3.
COOK NUCLEAR PLANT      - UNIT 2              3/4 3-47                AMENDMENT NO. '9&E 9S,


==4.0. 2axeapplicable==
totheabove'required frequencies forperforming insexvice inspection andtestingactivities.
Performance oftheaboveinservice inspection andtestingmctivities shallbeinadditiontootherspecified Surveillance Requirements.
e~4.0.6NothingintheASMEBoilerandPressureVesselCodeshallbecon-stxuedtosupersede therequirements ofanyTechnical Specification.
'ba,enganeeensonsorcernsurveancesrequiredtobeperormedgnorbefreMarh31,186,untitheendoftheCyc~e5-6efueliilg outageFor'sespcificseillanc)underthisectiothes$cifiedtimeinexvalsequiredySpecicatio4.0.2illbedetermiedwiththenenitia)ondateestablisedbtheurveilancedaedurintheUnit21984refuoutae.4.0.7Amendments 97and99grantedextensions forcertanreuiredtoeperformdonorbereJuly~1,1988,untiltheendofthCycle6-refueling utage.Fothesehecificseillanesundethissecon,thesecifiedteintelsrequirdbySpecication4..2willbedetermine withthnewinitationteestabli+edbythesurveilla cedatedngtheit219refueling outage.COOKNUCLEARPLANT-UNIT23/40-3AMENDMENT NO.7g,g7,131 1't) 340LXCSURVEILLANCE 4.0.8Byspecificreerencetossecton,osesurveanceswhichmustbeprformedonorbeforehut13,1994,andaredesignedas-monthr36-mosurvelancesorreedasouge-related seillansundetheprosionsoSpecifiation4..5)maybedeledunttheenofthecl'e9-10efuelioutage.Forthesespecicseillancsunderthissetion,speciiedtimeintelsreredbypecificaion4.0.willbdetermedwiththeneinitiatondatestablishdbythesurveillcedatduringth'eUnit21994efuelinoutae.4.0.9Byspecificreerencetossecton,osesurveanceswhi.chmusbeperformed onbeforeeptembr7,194,andadesitedas1monthh~eillanesmayedeladuntijustprortoreeloadnthetJqit2Cye9-10efuelioutaCOOKNUCLEARPLANT-UNIT23/40-4AMENDMENT NO.~,166 nOTB.E3-CTORISYSTSTE0SVCUFUNCTIONAL UNI1.ManualReactorTripA.ShuntTripFunctionB.Undervoltage TripFunction2.PowerRange,NeutronFlux3.PowerRange,NeutronFlux,HighPositiveRate4.PowerRange,NeutronFlux,HighNegativeRate5.Intermediate Range,NeutronFluxCHANNEL~GEEN.A.N.A.N.A.N.A.CHANNELC0N.A.N.A.(20)IM(I)andQ(608)R(6)R(6)'(6,8)CHANNELFUNCTIONAL
~AT.~S/U(1)(10)S/U(1)(10)MandS/U(l)S/U(l)MODESINWllICHSURVEILLANCE RUR3*,4*,5*3*,4*,5*1,2and*1,21,21,2and*aWo6.SourceRange,NeutronFlux7.Overtemperature AT8.Overpower AT9.Pressurizer Pressure--Low 10.Pressurizer Pressure--High ll.Pressurizer WaterLevel--High 12.LossofFlow-SingleLoopR(6,14)R(9)gR(9)e"ReRPaQR(8)M(14)andS/U(l)2(7),3(7),4and51,21,21,21,~21,2 r>t0 TABLE3.3-3Continued ENGINEERED SAFETYFEATURESACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNITMINIMUMTOTALNO.CHANNELSCHANNELSAPPLICABLE OFCHANNELSTOTRIPOPERABLEMODESACTION7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPStfla.SteamGenerator WaterLevel--Low-Low 3/Stm.Gen.2/Stm.2/Stm.1,2,3Gen.anyGen.2Stm.Gen.14*b.ReactorCoolantPumpBusUndervoltage 8.LOSSOFPOWERI4-1/Bus1,2,319*a.4kVBusLossofVoltage3/Bus2/Bus2/Bus1,2,3,414*b.4kVBusDegradedVoltage9~MANUAL3/Bus(QiA-(nfl'i721l)VIE+Qj2/Bus2/Bus1,2,3,414*(T7lbTmlnBj(T2lATm'+SiTz,ID-Twi<<)T't<D-<~'<4)a.SafetyInjection (ECCS)Feedwater Isolation ReactorTrip(SI)Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation Auxiliary Feedwater PumpsEssential ServiceWaterSystem2/train1/train2/train1,2,3,418b.Containment SprayContainment Isolation-Phase"B"Containment PurgeandExhaustIsolation Containment AirRecirculation Fan1/train1/train1/tra'in1,2,3,418c.Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation 1/train1/train1/train1,2,3,418d.SteamLineIsolation 2/steam2/steamline(1line(1pertrain)pertrain)2/opera-1,'2,3tingsteamline(1pertrain)20COOKNUCLEARPIANT-UNIT23/43-20AMENDMENT NOg7jfgg~137' 3/4..LIMI'HNGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTfONAL UNITl.SAFETYINIECIION, TURBINETRIP,FEEDWATER ISOLATION.
ANDMOTORDRIVENAUXILIARY FEEDWATER PUMPSCHANNELCfiANNELCHANNELFUNCTIONAL CHECKCALIRAIIDHIEEI'RIPACTUATING DEVICEOPERATIONAL MODESINWHICHSURVEILLANCE SQUIREDa.ManualInitiation b.Automatic Actuation Logicc.Containm<<nt Pressure-Highd.Pressurixcr Prcssurc-Lowc.DifFerential PressureBctwccnSteamLines-Highf.StcamLuePressure-Low2.CONTAINMENT SPRAYa.ManualInitiation b.Automatic Actuation Logicc.Concunmcnt Pressure-High.High3.CONTAINMENT ISOLATION a.Phase'AIsolation N.A.N.A.N.A.N.A.M(3)N.A.N.A.N.A.N.A.SceFunctional Unit9M(2)N.A.M(3)N.A.SccFunctional Unit9M(2)N.A.I,2,3,41,2,3I,2,3I,2,31,2,31,2,3,41,2,3I)Manual2)FromSafetyInjection Automatic Actuation Logic'.PhaseB'solation N.A.N.A.SccFunctional Unit9M(2)N.A.1,2,3,4I)Manual2)Automatic Actuation Logic3)Containmcnt Pressure-f{igh.HighN.A.SSccFunctional Unit9M(2)M(3)N.A.N.A.1,2,3,41,2',3COOKNUCLEARPLANT-UNIT 2Pago3/43-30AMENDMENT 34,434,4K,158 CJ 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNITc.PurgeandExhaustIsolation CHANNELCHANNELCHANNELFUNCTIONAL CHECKCALIBRATION TESTlTRIPACTUATING DEVICEOPERATIONAL TESTMODESINWHICHSURVEILLANCE
~REUlREDI)Manual2)Containment Radioactivity
-HighSccFunctional Unit9-N.A.1,2,3,44.STEAMLINEISOLATION a.Manual-SecFunctional Unit9--b.Automatic Actuation Logicc.Containmcnt Pressurc-High-High d.SteamFlowinTwoSteamLines-HighCoincident withT,,-Low-Lowc.SteamLinc'Prcssurc-LowS.TURBINETRIPANDFEEDWATER ISOLATION a.SteamGenerator WaterLevel-High-High N.A.N.A.M(2)M(3)N.A.N.A.N.A.N.A.N.A.I,2,3I,2,3I,2,31,2,31,2,36.MOTORDRIVENAUXILIARY FEEDWATER PUMPSa.StcamGenerator iVaterLevel-Low-Lowb.4kVBusLossofVoltagec.SafetyInjection d.LossofMainFeedPumpsN.A.N.A.N.A.N.A.M(2)N.A.N.A.I,2,3I,2,3I,2,31,2"%teart)vhion~~tnicaLSpcciiieatiea-4A)A Ltpplicable.
COOKNUCLEARPLANT-UNIT 2Page3/43-31AMENDMENT aI,&,434,434,4W,459,16S Pk0 3/4.3.3KOH~~OEIHC GiSTM~LTION LXKKTZSCCOHDZTZOS FOEQPKLLTIQS 3.3.3.1Thara~~~mcraiarz~
~~~mantas~mn
~mn~ahcncnTahoe3.~ahaU.beQPKLL'.KZ
~~~/~sespo~W~the)spec'~~~4CXEZLZZT:
haabc'Tabb<3.~.JCXZOE:a.V'Aa~~non'~~channelakaxa/a~aespoinsczcaa~thavaLaasheewTable3.M,adgnos~aetpo~toMahdithaXfad.tW~4boersorde~athachannelfmoperabIa.
bo%~AoneoTnccet~~~celt?ftoT~
ch@nL'eezabla,rakethe~HebcncafaTabl.a3.~.c.Thepmvta~ofSpe~caeLana 3.0.3cad3.0.4arenotapylfcabLa.4.3.3.1EachzmLfaahan zoon"metalc1nnuaakahaLlbeasshefx'eqnencMs abneriaTabLa4.33.~i~ehQca1~H4ng-osage D,C.CQOK~23/4334A$EtldQolTC
)f0~43 riOOc<riXuasauumr:
ir1.SteamGenerators 1and4LevelV000GV~GVES&#xb9;LE~041CabinetlandLSICabinet4ClhNNEL~CWCQCllANNELC02,SteamGenerators 2and3LovelLSICabinet2andLSICabinet43.SteamGenerators 1and4ProssureLSICabinet4andLSICabinet5SteamGenerators 2and3PressureLSICabinet4andLSICabinet65,ReactorCoolantLoop4Temperature (Cold)6.ReactorCoolantLoop4Temperature (llot)LSICabinet4andLSICabinet5LSICabinet4andLSICabinet5Ry)7,ReactorCoolantLoop2Temperature (Cold)LSICabinet4andLSICabinet68.,RoactorCoolantLoop2Temperature (llot)LSICabinet4andLSICabinet6eg09.Pressurizer Lovel.10.RaactorCoolantSystemPressurell.ChargingCross-Flow BetweenUnitsLSICabinet3LSICabinet3gorridorKiev.587'/aR'2.SourceRangeNeutronDetector(N-23)LSICabinet4n/a*CbargingGross-1'low betweenUnitsisaninstrpment commonto'bothUnit1and2,Tbissurveillance villonlyboconducted onanintervalconsistent MithUnit1refueling.
wuhlI r>
BL3-0OS-COlTORINGSEAT00VUEECJNNHEL~CEEC1.2~3~4,5.6.7~8.9.10'1.12~13.14.15.16.17~1B.Containment PressureReactorCoolantOutletTemperature
-Tgp)(HideRange)ReactorcoolantInletTemperature
-T<<,p(HideRange)ReactorCoolantPressure-HideRangePressurizer WaterLevelSteamLinePressureSteamGei>orator HaterLevel-NarrowRangeBHSTWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator
-LimitSwitchesPORVBlockValvePositionIndicator
-LimitSwitchesSafetyValvePositionIndicator
-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)
ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)
Containment SumpLevelContainment HaterLevelMMMMMMMMMMMMMMMM(2)MMR+RRRRRR(1)%'(3)P RPartialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.(2)(3)HithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.
Completion ofchannelcal'ibration forsensorstobe.performed belowP-12inMODE3.COOKNUCLEARPLANT-UNIT23/43-47AMENDMENT NO.'9&E9S,
~>
~>
CDnCDCD7C1STSAMPLE.1NSPECTlON TABLE4.4-2STEAMGENERATOR TUBEtNSPECTION 2NDSAMPLElNSPECTION 3ADSAMPLEINSPECTION SaintitoSireAcauliActicinltcituircd ResultAcriuntt'oquircd AcauliAclionAcquucdAminunumolSTubestierS.G.C-1C-2C-3NuiiePtuadclcclive lubcaandlnspecledititionat 2SlubestnllusS.G.tnstiectalltutiesrnttuaS.G..l)lugUelocllvetubesaililtnsticct2SlubesincactiotlicrS.G.Promtllnultticallon toNACpursuanttospecilication 69.1NIAC-1C-2C-3AtlalberSGiseicClSameS.G.sC-2butnoadditional S.G.aieC-3Additional S.G.iaC-3NIANnnePhag'detective tubesaiidiniticclaitititianat 4StubesuiltwsS.G.PciloimaclioiilorC-3resultollullaamtiteNonePcilormac(iantbrC-2resultolsecondtnspoctalllubeaineachS.G.andpkrydelectivetubes.Promptnolilicatlon loNRCpursuantlospecilicalian G.Q.IN/ANIAC-1C-2NIANIANIANIANIANoneNIANIANIANIANIAPtugdetective lulieaPcrloimactiontorC-3resultollustsamtite3N<ShoreHlatlienumberolstcamttaneratora tnlheunit,anditlslhenumberolsteamtteneiatora
TABLE 4.4-2 CD n
<<specteriluitnQJntnrtioctlon C
STEAM GENERATOR TUBE tNSPECTION CD CD 7C            1ST SAMPLE. 1NSPECTlON                                2ND SAMPLE lNSPECTION                    3AD SAMPLE INSPECTION Saintito Sire      A cauli          Acticin ltcituircd        Result        Acriun tt'oquircd         Acauli        Aclion Acquucd A minunum ol          C-1                  Nuiie                  NIA                NIA                  N/A                NIA S Tubes    tier S. G.
REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLVPPSYSTEMLLQCAGEL~QCAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1Thefollowing ReactorCoolantSystem,leakagedetection syseemsshallbeOPERABLE:
C-2        Ptua dclcclive lubca          C-1                Nnne                  NIA                NIA and lnspecl edititionat                    Phag'detective tubes          C-1        None 2S lubes tn llus S. G.       C-2          aiid initiccl aitititianat    C-2        Ptug detective luliea 4S tubes ui ltws S. G.
a.Oneofthecontainmene atmosphere particulate radioactivity monitoring'hannels (ERS-2301 orERS-2401),
Pcrloim action tor C-3 result ol lust samtite Pciloim aclioii lor C-3        C-3 result ol lull              NIA                NIA aamtite C-3        tnstiect all tuties rn      Atl alber ttua S. G.. l)lug Ue        S Giseic              None                NIA                NIA locllve tubes ailil        C l tnsticct 2S lubes in      Same S. G.s Pcilorm ac(ian tbr cacti otlicr S. G.                                                       NIA                NIA C-2 but no C-2      result ol second additional Promtll nultticallon      S. G. aie to NAC pursuant            C-3 to specilication          Additional    tnspoct all lubea in 6 9.1                    S. G. ia C-3  each S. G. and pkry d elective tubes.
b.Thecontainment sumplevelandflowmonitoring system,andc.Eitherehecontainmene humiditymonitororoneofthecontainmene atmosphere gaseousradioactivity monitoring channels(ERS-2305 orERS-2405).
Prompt nolilicatlon              NIA                NIA lo NRC pursuant lo specilicalian G.Q.I 3
APPLICABILITY:
N
MODES1,2,3and4ACTION'ith onlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation mayconeinueforupto.30daysprovidedgrabsamplesofthecontainmene atmosphere areobtainedandanalyzedatleaseonceper24hourswhen~~~~eherequiredgaseousand/orparticulate radioactivity monieoring channelsareinoperable; otherwise, beinatleaseHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwiehinehefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonserated OPERABLEby:a~Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-perfonnance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3,b.Containmene sumplevelandflowmonitoring syseem-performance ofCHANNELCALIBRATION aeleastonceper18months,c~Containmene humidieymonitor(ifbeingused)-performance ofCHANNELCALIBRATION aeleaseonceper18"months.
                < Shore  H la tlie number ol    stcam ttaneratora tn lhe unit, and it ls lhe number    ol steam tteneiatora <<specter iluitnQ Jn tnrtioctlon
COOKNUCL<<RPLANT-UNIT23/44-14AMENDMENT NO.W,~,159 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE RE<QUIRL<MI<
 
NTS('/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION Continued WithPORVsandblockvalvesnotinthcsamelineinoperable duetocausesotherthanexcessive seatleakage,within1hourrestorethevalvestoOPERABLEstatusorcloseanddc-energize theassociated blockvalveandplacetheassociated PORVinmanualcontrolineachrespective line.ApplytheportionsofACTIONcordabove,relatingtotheOPERATIONAL MODE,asappropriate fortwoorthreelinesunavailable.
C REACTOR COOLANT SYSTEM 3/4.4.6          REACTOR COOLVPP SYSTEM LLQCAGE L~QCAGE DETECTION SYSTEMS LIMITING CONDITION          FOR OPERATION 3.4.6.1            The following Reactor Coolant System, leakage detection        syseems                  shall be OPERABLE:
h.Theprovisions ofSpecification 3.0.4arenotapplicable.
: a.     One of the  containmene atmosphere     particulate radioactivity or ERS-2401),
SURVEILLANCE REUIREMENTS 4.4.11.1Inadditiontotherequirements ofSpecification 4.0.5,eachPORVshallbcdemonstrated OPERABLE:
monitoring'hannels (ERS-2301
Atleastonceper31daysbyperformance ofaCHANNELFUNCTIONAL TEST,excluding valveoperation, andAtleastonceper18monthsbyoperating thePORVthroughonecompletecycleoffulltravelduringMODES3or4,andc.Atleastonceper18monthsbyoperating solenoidaircontrolvalvesandcheckvalvesinPORVcontrolsystemsthroughonecompletecycleoffulltravel,andAtleastonceper18monthsbyperforming aCHANNELCALIBRATION ofthcactuation instrumentation&
: b.     The containment sump      level and  flow monitoring system,   and
4.4.11.2Eachblockvalveshallbcdemonstrated OPERABLEatleastonceper92daysbyoperating thevalvethroughonecompletecycleoffulltravelunlesstheblockvalveisclosedinordertomeettherequirements ofACTIONb,c,ordinSpecification 3.4.11.4.4.11.3Deleted.f-'Feehnieal-Speei6eatie licable.COOI(NUCLEARPLANT-UNIT 2Page3/44-33AMENDMENT 4W,~,4W,444,196 it
: c.     Either  ehe containmene humidity monitor or one of the containmene atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).
'~4~~4.4.12.1BothReactorVesselheadventpathsshallbedeaanstrated OPEleastonceper18monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.
APPLICABILITY:           MODES  1, 2,   3  and 4 ACTION'ith only two of the above required leakage detection systems OPERABLE, operation may coneinue for up to.30 days provided grab samples of the containmene atmosphere are obtained and analyzed at lease once per 24 hours when
2.CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulLtravelfromtheControlRoomwhileinNodes5or6~3.Verifying floethroughbothoftheReactorVesselheadventpathsduringventingoperation, awhileinNodes5or6.Surveillan erequintstodnstratethe,operabilit ofeacheactorVeselheadvetpathbeperfoHthenextimetheuttersNOD5or6folingthesuanceofTechnicSpfication, andafterheapproprtePlantpcedureshaebeenm'iten.D.C.COOK-terr23/44-35amencunent Wo.65 r>
            ~
4.4.12.2BethPrsurizersteamspaceventpathsshallbedemonstrated OPBKLBLatleastonceper18monthsby:1~Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.
ehe required gaseous and/or particulate radioactivity monieoring channels are
CyolingeachofthereaetelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.rISurveill+ce requireme todemotratethepdrability ofhPressurizer steamspeventpawillbeformedthentimeHeunitenersMODES5or6folingtheiuanceoftechnicSpeoifgcation, anafterthappropria Plantproceshaveenwritt~~0.C.COOK-UHZT23/44-37Amenchnent No.65 EMERGENCY CORECOOLINGSYSTEMS~~SURVEILLANCE REUIREMENTS 4.5.2EachECCSsubsystem shallbedemonstrated OPERABLE:
                ~
a.At1'eastonceper12hoursbyverifying thatthefollowing valvesareintheindicated positions withpowertothevalveoperators removed:ValveNumberValveFunctionValvePositiona.IMO-390b.IMO-315c.IMO-3250d.Q-262*e.IN-263*f.IMO-261*g.ICM-305*h.ICM-306*a.RWSTtoRHRb.LowheadSItoHotLegc.LowheadSItoHotLegd.Miniflowlinee.Miniflowlinef.SISuctiong.SumpLine,h.SumpLinea.Openb.Closedc.Closedd.Opene.Openf.Openg.Closedh.Closedb.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic}
inoperable; otherwise, be in at lease HOT STANDBY within the next 6 hours and in
intheflowpaththatisnotlocked,sealed,or~othersesecuredinposition, isinitscorrectposition.
~                                    ~
c.Byavisualinspection whichverifiesthatnoloosedebris(rags,tx'ash,clothing, etc.}ispresentinthecontainment whichcouldbetransported tothecontainment sumpandcauserestriction ofthepumpsuctionsduringLOCAconditions.
COLD SHUTDOWN wiehin ehe following 30 hours.
Thisvisualinspection shallbeperformed:
SURVEILLANCE RE UIREMENTS 4.4.6.1            The leakage  detection systems shall be demonserated        OPERABLE                by:
1."Forallaccessible areasofthecontainment priortoestablishing CONTAINMENT INTEGRITY, and2.Oftheareasaffe'cted withincontainment atthecompletion ofeachcontainment entrywhenCONTAINMENT INTEGRITY isestablished.
a ~   Containment atmosphere     particulate and gaseous (if being used) monitoring system-perfonnance       of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,
esevalvesmustchangepositionduringtheswitchover frominjection torecirculation flowfollowing LOCA.COOKNUCLEARPLANT-UNIT23/45-4AMENDMENT N0.7$,$3$
: b.     Containmene sump    level  and flow monitoring syseem-performance                       of CHANNEL CALIBRATION ae      least  once per 18 months, c ~   Containmene humidiey monitor      (if  being used) - performance   of                  CHANNEL CALIBRATION ae lease once per 18"months.
COOK      NUCL<<R PLANT - UNIT        2            3/4 4-14            AMENDMENT NO. W,                   ~,   159
 
('/4.4 3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE RE<QUIRL<MI<NTS REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION Continued With PORVs and block valves not in thc same line inoperable due to causes other than excessive seat leakage, within 1 hour restore the valves to OPERABLE status or close and dc-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.
: h.     The provisions    of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.11.1                In addition to the requirements of Specification 4.0.5, each PORV shall bc demonstrated OPERABLE:
At least once per 31 days by performance        of a  CHANNEL FUNCTIONAL TEST, excluding valve operation, and At least once per 18 months by operating the PORV through one complete cycle        of full travel during MODES 3 or 4, and
: c.       At least once per  18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and At least once per 18 months by performing a CHANNEL CALIBRATION of thc actuation instrumentation&
4.4.11.2              Each block valve shall bc demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.11.
4.4.11.3              Deleted.
f-'Feehnieal-Speei6eatie                 licable.
COOI( NUCLEAR PLANT-UNIT2                        Page 3/4 4-33        AMENDMENT4W,         ~, 4W, 444,     196
 
i t
 
4
  ~
  ~   ~
4.4.12.1  Both Reactor Vessel head vent paths        shall  be deaanstrated  OPE least once per 18 months by:
Verifying the  common manual    isolation valve in the Reactor vessel head vent  is sealed  in the open  position.
: 2. Cycling each of the remotely operated valves in each path through at least  one complete cycle of fulL travel from the Control Room while in  Nodes 5  or  6~
: 3. Verifying floe through both of the Reactor Vessel        head  vent paths during venting operation, awhile in Nodes 5 or 6.
Surveillan e requi        nts to d nstrate the, operabilit of each eactor Ves el head ve t path            be perfoH      the next ime the u      t ters NOD 5 or 6 fol ing the suance of                  Technic Sp      fication, and after he appropr te Plant p cedures ha e been m'i ten.
D. C. COOK - terr  2                    3/4 4-35                          amencunent Wo. 65
 
r>
4.4.12.2  Beth Pr    surizer steam space vent paths shall be demonstrated OPBKLBL      at least once per 18 months by:
1 ~   Verifying the  common manual  isolation valve in the Pressurizer steam space vent is sealed in the open position.
Cyoling each of the reaetely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
3   . Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.
r I
Surveill+ce requireme       to demo  trate the pdrability of        h Pressurizer    steam sp  e vent  pa  will be    formed the  n    time    He unit    en ers MODES 5 or 6  fol ing the i uance of t            echnic Speoifgcation, an after th appropria          Plant proc    es have    en writt 0.~ C. COOK - UHZT 2                    3/4 4-37                          Amenchnent No. 65
 
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2
~  ~      Each  ECCS  subsystem  shall be demonstrated  OPERABLE:
: a. At 1'east once per 12 hours by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number            Valve Function            Valve Position
: a. IMO-390              a. RWST  to RHR          a. Open
: b. IMO-315              b. Low head SI          b. Closed to Hot Leg
: c. IMO-325              c. Low head SI          c. Closed 0                      to Hot Leg
: d. Q-262*             d. Mini flow line        d. Open
: e. IN-263*             e. Mini flow line        e. Open
: f. IMO-261*             f. SI Suction            f. Open
: g. ICM-305*           g. Sump  Line,          g. Closed
: h. ICM-306*             h. Sump  Line            h. Closed
: b. At least once per 31 days by verifying that each valve (manual, power operated or automatic} in the flow path that is not locked, sealed, or
          ~
other se secured in position, is in its correct position.
: c. By a  visual inspection which verifies that no loose debris (rags, tx'ash, clothing, etc.} is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during    LOCA  conditions. This visual inspection shall be performed:
1."  For  all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY,      and
: 2. Of the areas affe'cted within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
ese valves must change position during the switchover from injection to recirculation flow following LOCA.
COOK NUCLEAR PLANT -      UNIT 2              3/4 5-4            AMENDMENT N0.7$ ,$ 3$
 
ee GENCY COR  COOL  G  S  S SURVe.ELLANCE      R Cc.5.3el The
    ~    ~      ECCS  subsystem shall be demonstrated OPERABLE per the  applicable Sn~eillence    Reqnizenence e= 4.5.2.Oe.
4.5.3.2 All charging    pumps and safety in]ection pumps,  except tne above required OPERABLE  charging pump, shall be demonstrated  inoperable, by verifying that the motor circuit breakers have been removed from    their elecMcal po~er supply circuits, at least once per 12 hours vhenever    the temperature of one or more of "the RCS cold legs is less than or equal to  152 F as determined at least once per hour ~hen any RCS cold leg temperature is    between 152'F and 200 F.
v COOK HUCLZAR PLANT    - UNXT 2          3/c& 5-8
 
CO          SYS  S URVEILLANCE E    REMENTS  Co tinued C ~  At least  once per 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure--High-High test signal+.
: d. At least once per 5 years by verifying a water flow rate of at least 20 gpm (greater than or equal to 20 gpm) but not to exceed 50 gpm (less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255 psig.
chnM~peci-                    re-appkkcab1e.
COOK NUCLEAR  PIANT - UNET 2          ~
3/4 6-12    AMENDMENT NO. 4Sg Mf 48k)  15
 
CONTAINM NT SYSTEMS SURVE    LANCE  R UIREMENTS      Continued 4.6.3. 1.2  Each containment    isolation valve shall be demonstrated  OPERABLE during the    COLD SHUTDOHH  or  REFUELING NODE at least once per IG  months by:I
: a. Verifying that on a Phase A containment isolation test signal, each Phase  A isolation valve actuates to its isolation position.
: b. Verifying that on a Phase B containment isolation test signal,.
each Phase B isolation valve actuates to its isolation position.
: c. Verifying that  on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation, position.
4.6.3. 1.3  The isolation time of each power operated or automatic containment isolation valve 'shall be determined to be within its limit when tested pur suant to Specification 4.0.5
~e-pmv4~-ien~Meeh
                              'OOK NUCLEAR PLANT  UNIT 2              3/4 6-14          AMENOMENT NO. 97, 43k 458, 165
 
CO  A DW    ARRI    S G COND  +0              ON 3.6.5.9 The divider barrier seal shall    be OPERABLE.
With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.
VE      C  RE 4.6.5.9 The divider barrier seal shall be determined    OPERABLE  at least once per 18 months during shutdown by:
: a. Removing two  divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.
: b. Visually inspecting at least  95  percent of the seal's'.entire length and:
Verifying that the seal  and seal mounting  bolts are pro-perly installed, and
: 2. Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.
COOK NUCLEAR PLANT    - UNIT  2    3/4 6-47            AVOND~ NO. M,
 
P LANT SYSTEMS 3  4 7 3  COMPONENT COOL NG WA ER S      S TING    COND TIO      0  OPERATION 3.7.3.1
: a. At least two independent      component cooling water loops shall be    OPERABLE.
: b. At least one component cooling water flow path in support of Unit          1 shutdown functions shall be available.
Specification 3.7.3.1.b. - At      all times when Unit 1  is in  MODES  1, 2, 3, or 4.
~CT ON:
When    Specification 3.7.3.1.a .is applicable'.
With only one component cooling water loop              OPERABLE,  restore at least two loops to OPERABLE status within 72 hours          or be in at least HOT    STANDBY within the next 6 hours and    in  COLD SHUTDOWN within the      following 30 hours.
When    Specification 3.7.P.l.b is applicable:
3o With no flowpath & Unit 1 available, return at least one flowpath to available status ithin 7 days, or provide equivalent shutdown capabil'ity in Unit 1 and return at least e flow path to available-status within-the next 60 days, or have-Unit 1 in HOT ANDBY within the next 12 hours and HOT SHUTDOWN within the following 24 hours.                 The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.3.1        At least two    component  cooling water loops shall be demonstrated      OPERABLE:
: a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
: b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing sagety related eguipment actuates to its correct position on a Safety Infection test signal.g C'. by Verifying Pumt feepm'<~              Pung'~ % SPCt4C.Wk~ 'I,Od5.
At least once per 18 months during shutdown, verify that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.
OK NUCLEAR PLANT        - UNIT  2                3/4 7-12          AMENDMENT NO. M,    4k@,
158
 
  ~ ~
0 I
1
 
~
C 3  4.7.4    ESSENTIAL SERVICE    WATER SvSTEYt LIMITING CONDITION          FOR OPERATION 3.7.4.1
: a. A  least  two independent  essential service water loops shall be OP~MI >.
: b. At least one essential service water flowpath associated with support of Unit 1 shutdown functions shall be available.
APPLICABILITY:          Specification 3.7.4.1.a. - MODES 1, 2, 3, and 4.
Specification 3.7.4.1.b. - At all times when Unit    1 is in  MODES 1, 2, 3, or 4.
ACTION'hen Specification 3.7.4.1.a is applicable:
With only one essential service ~ater loop OPERABLE; restore at. least two loops to .
OPERABLE status within 72 hour's or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
When      Specification 3.7.4.l.b is applicable:
With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one flow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours and HOT SHUTDOWN within the following 24 hours. The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIRENENTS 4.7.4.1        At least    two  essential service water loops shall  be demonstrated  OPERABLE:
ae  At least  once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
: b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test sitnalQff
                                                                  ~ ~ ~      -                ~ ~
                                                                                                    ~ ~
c    a COOK NUCL:"4Z. PI      MT  - UNIT 2                3/4 7-13
 
3/4  LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued
: e. At least once per  18 months  by:
: 1.      Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
: 2.      a.      Verifying that on a Safety Injection Signal from Unit 1, the system automatically operates in the pressurization/cleanup mode.&
: b.      Verifying that on a Safety Injection Signal from Unit 2, the system automatically operates in the pressurization/cleanup mode.
: 3.      Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W. G. relative to the outside atmosphere at a system flow rate of 6000 cfm'plus or minus 10%.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
plieable.
COOK NUCLEAR PLANT-UNIT2                Page 3/4 7-16a                AMENDMENT&, 434, 488, 202
 
3/4.7    7 SNUBBERS IHITINC CONDITION      FOR OP  ATION 3.7.7.1      All safety-related    snubbers  shall be  OP~~"LZ.
systems required OPERABLE    in those MODES).
~CT la Pith  one or more snubbex's inoperable, within 72 hours x'eplace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that    system.
SURVE  L  NC  RE UIR    NTS
                                                                          ~  C 4.7.7.1      Each snubber shall be demonstrated OP~~LE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a      Visual ns ectio Snubbers    are categorized as inaccessible or accessible during reactor operation.      Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-9. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-9 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before  Amendment No.  ~.
: b. Visual Ins ection    Acce tance  Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.'Snubbers which appear inoperable as'        result of visual inspections shall be classified as unacceptable and may be reclassified as acceptable for the purpose of establishing the next visual inspection interval," providing that (1) the cause of the rejection is clearly established and remedied for that COOK NUCLEAR PLANT  UNIT 2                3/4 7-20      AMENDMENT NO. 492,~'-, ~    159
 
ELECTRICAL    POUTER  SYSTEHS SHUTDOWN LIHITINC COND TIQN      FOR OPERA    ION 3.8.1.2 As a      minimum, the    following A.C. electrical    power sources snail 'oe OPERABI-'ne circuit between the offsite transmission        network and the onsite Class    1E distribution system, and
: b. One  diesel generator with:
: 1. A day  fuel tank containing      a mintuaun of 70 gallons of fuel,
: 2. A  fuel 'storage system containing      a minimum indicated volume of 46,000 gallons      of fuel, and
: 3. A  fuel transfer    pump.
ACTION Pith less than the above minimum required A.C. electrical power"sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive
-reactivity changes+ until the minimum required A.C. electrical power sources are restored to      OPENABLE  status.
SURVEIL'LANCE RE UI EHENTS 4.8.1.2  The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.5.            f
* For  purposes of this specification, addition of water from the RWST does not constitute    a positive reactivity addition provided the boron concentration in the RUST is greater than the minimum required by Specification 3.1.2.7.b.2.
The COOK  NUCL:"M PLANT - UNIT      2            3/4 8-9          AHENDHENT NO. 4M, Ma. 159
 
~ p 3/4.0  LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 'LECTRICALPOWER              SYSTEMS SURVEILLANCE RE UIREMENTS Continued t
: b.      At least once per 92 days by verifying that:
: 1.        The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.
The specific gravity, corrected to /7'F, and full electrolyte level (fluid't the bottom of the maximum level indication mark), of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and
: 3.        The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.
At least once per  1&  months by verifying that:
: 1.      The cells, cell plates and battery racks show no visual indication  of physical damage or abnormal deterioration, The  cell-to~ll and terminal connections are clean, tight, free of corrosion  and coated with anti-corrosion material, f
: 3.        The battery charger will supply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours.
At least once per 18 months, perform a battery service test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2. The battery charger will be disconnected throughout the test. The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this  test~
At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.
Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.
Degradation is indicated when the battery capacity drops morc than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. If the bauery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.
Mte-provisions-ef-Specif cati              a  licable COOK NUCLEAR PLANT-UNIT2                        Page 3/4 8-13                AMENDME<NT443, 439, 4@i, 183
 
3/4.0    LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8    ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.2.4        As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:
1 - 250-volt D.C. bus,  and 1 - 250-volt battery bank and charger associated with the above D.C. bus.
APPLICABILITY:          MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours.
SURVEILLANCE RE UIREMENTS 4.8.2.4.1      The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2      The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.~
e-epplieabl                        ttirtnncnt
+242 X2.cLfowho4-C~wtte~~+dtargcr.
COOK NUCLEAR PLANT-UNIT2                        Page 3/4 8-15                  AMENDMENT443,        4', 183
 
3.9.12    The  spent fuel storage pool exhaust      ventilation        system    shall  be OPERABLE.
whenever  irradiated fuel is in the storage pool.
Pith  no  fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*
: b. The  provisions of Specifications 3.0.3 and 3.0 '              are not applicable.
S 'RV    VC  R  U      ITS 4.9.12  The above    required fuel storage pool ventilation system shall                be demonstrated  OPERABLE:
: a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying -hat the train operates for at least 15 minutes.
: b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
: 1. Deleted.
: 2. Verifying that the charcoal adsorbers remove ) 99% of a halogenated hydrocarbon -,refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flaw rate of 30,000 cfm + 10%.
clqqr og ~  clvxl l I+
gillie  QALac 4%
The crane bay    roll-up  door and the                                          may be opened under administrative    control. during  movement    of  fuel    within    the  storage pool or crane. operation with    loads  over the    storage  pool.
Shared system    with  D. C. COOK - UNIT 1.
This does not include the main load block. For purposes of this specification, a deenergized main load block need not be considered                    a  load.
,     C. COOK - UNIT 2                          3/4 9-12            Amendment No              111


eeGENCYCORCOOLGSSSURVe.ELLANCE RCc.5.3elTheECCSsubsystem shallbedemonstrated OPERABLEpertheapplicable
5.0    DESIGN FEATURES 5.6 FUEL STORAGE Continued CRITICALITY- SPENT FUEL Continued The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations'an~mphieai~ieted=in=Rgtt~~
~~Sn~eillence Reqnizenence e=4.5.2.Oe.
For Re ion 2 Stora    e Minimum Assembly Average Burnup in MWD/MTU =
4.5.3.2Allchargingpumpsandsafetyin]ection pumps,excepttneaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable, byverifying thatthemotorcircuitbreakershavebeenremovedfromtheirelecMcalpo~ersupplycircuits, atleastonceper12hoursvheneverthetemperature ofoneormoreof"theRCScoldlegsislessthanorequalto152Fasdetermined atleastonceperhour~henanyRCScoldlegtemperature isbetween152'Fand200F.vCOOKHUCLZARPLANT-UNXT23/c&5-8 COSYSSURVEILLANCE EREMENTSCotinuedC~Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaContainment Pressure--High-High testsignal+.d.Atleastonceper5yearsbyverifying awaterflowrateofatleast20gpm(greaterthanorequalto20gpm)butnottoexceed50gpm(lessthanorequalto50gpm)fromthesprayadditivetanktestlinetoeachcontainment spraysystemwiththespraypumpoperating onrecirculation withapumpdischarge pressuregreaterthanorequalto255psig.chnM~peci-re-appkkcab1e.
                                -22,670 + 22,220 E-2,260 E +          149 E For Re ion 3 Stora    e Minimum Assembly Average Burnup in MWD/MTU =
COOKNUCLEARPIANT-UNET2~3/46-12AMENDMENT NO.4SgMf48k)15
                                -26,745 + 18,746 E- 1,631 E2 + 98.4        E3 Where E  = Initial Peak Enrichment 5.6.1.2      Fuel stored in the spent fuel storage raCks shall have a nominal fuel assembly enrichment as follows:
Maximum Nominal Fuel Assembly Enrichment Description                                                Wt. % U-235
: 1)       Westinghouse            15  x 15  STD                            4.95 15 x  15  OFA
: 2)       Exxon/ANF              15 x  15                                4.95
: 3)      Westinghouse            17 x  17  STD                            4.95 17 x  17  OFA 17 x  17  V5
: 4)      Exxon/ANF              17 x  17                                4.95 COOK NUCLEAR PLANT-UNIT2                        Page  54            AMENDMENT44, 424, 447,          4',  198


CONTAINMNTSYSTEMSSURVELANCERUIREMENTS Continued 4.6.3.1.2Eachcontainment isolation valveshallbedemonstrated OPERABLEduringtheCOLDSHUTDOHHorREFUELING NODEatleastonceperIGmonthsby:Ia.Verifying thatonaPhaseAcontainment isolation testsignal,eachPhaseAisolation valveactuatestoitsisolation position.
                                                          '3 r
b.Verifying thatonaPhaseBcontainment isolation testsignal,.eachPhaseBisolation valveactuatestoitsisolation position.
L"=
c.Verifying thatonaContainment PurgeandExhaustisolation signal,eachPurgeandExhaustvalveactuatestoitsisolation, position.
BUrc%lP  MAN
4.6.3.1.3Theisolation timeofeachpoweroperatedorautomatic containment isolation valve'shallbedetermined tobewithinitslimitwhentestedpursuanttoSpecification 4.0.5~e-pmv4~-ien~Meeh
    '9 4~
'OOKNUCLEARPLANT-UNIT23/46-14AMENOMENT NO.97,43k458,165 COADWARRISGCOND+0ON3.6.5.9ThedividerbarriersealshallbeOPERABLE.
C
Withthedividerbarriersealinoperable, restorethesealtoOPERABLEstatuspriortoincreasing theReactorCoolantSystemtemperature above200'F.VECRE4.6.5.9Thedividerbarriersealshallbedetermined OPERABLEatleastonceper18monthsduringshutdownby:a.Removingtwodividerbarriersealtestcouponsandverifying thatthephysicalproperties ofthetestcouponsarewithintheacceptable rangeofvaluesshowninTable3.6-2.b.Visuallyinspecting atleast95percentoftheseal's'.entire lengthand:2.Verifying thatthesealandsealmountingboltsarepro-perlyinstalled, andVerifying thatthesealmaterialshowsnovisualevidenceofdeterioration duetoholes,ruptures, chemicalattack,abrasion, radiation damage,orchangesinphysicalappearances.
~Z      CCC r
COOKNUCLEARPLANT-UNIT23/46-47AVOND~NO.M, P
u            p p xi~cc r o
LANTSYSTEMS3473COMPONENT COOLNGWAERSSTINGCONDTIO0OPERATION 3.7.3.1a.Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.
2             Los
b.Atleastonecomponent coolingwaterflowpathinsupportofUnit1shutdownfunctions shallbeavailable.
(   tl ~E  I iA
Specification 3.7.3.1.b.
                                              ~ ~
-AtalltimeswhenUnit1isinMODES1,2,3,or4.~CTON:WhenSpecification 3.7.3.1.a
f.4 . 14    LO  LS  LO    A      +A    44
.isapplicable'.
            . ~
Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.P.l.b isapplicable:
IN~i.BlRlCHMKHT, %U-235 5-8
3oWithnoflowpath&Unit1available, returnatleastoneflowpathtoavailable statusithin7days,orprovideequivalent shutdowncapabil'ity inUnit1andreturnatleasteflowpathtoavailable-status within-the next60days,orhave-Unit 1inHOTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:
a.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing sagetyrelatedeguipment actuatestoitscorrectpositiononaSafetyInfection testsignal.gC'.byVerifying Pumtfeepm'<~Pung'~%SPCt4C.Wk~
'I,Od5.Atleastonceper18monthsduringshutdown, verifythattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.
OKNUCLEARPLANT-UNIT23/47-12AMENDMENT NO.M,4k@,158
~~0I1
~C34.7.4ESSENTIAL SERVICEWATERSvSTEYtLIMITINGCONDITION FOROPERATION 3.7.4.1a.Aleasttwoindependent essential servicewaterloopsshallbeOP~MI>.b.Atleastoneessential servicewaterflowpathassociated withsupportofUnit1shutdownfunctions shallbeavailable.
APPLICABILITY:
Specification 3.7.4.1.a.
-MODES1,2,3,and4.Specification 3.7.4.1.b.
-AtalltimeswhenUnit1isinMODES1,2,3,or4.ACTION'hen Specification 3.7.4.1.a isapplicable:
Withonlyoneessential service~aterloopOPERABLE; restoreat.leasttwoloopsto.OPERABLEstatuswithin72hour'sorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.4.l.b isapplicable:
Withnoessential servicewaterflowpathavailable insupportofUnit1shutdownfunctions, returnatleastoneflowpathtoavailable statuswithin7daysorprovideequivalent shutdowncapability inUnit1andreturntheequipment toservicewithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIRENENTS 4.7.4.1Atleasttwoessential servicewaterloopsshallbedemonstrated OPERABLE:
aeAtleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsitnalQff
~~~-~~~~caCOOKNUCL:"4Z.
PIMT-UNIT23/47-13


3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSSURVEILLANCE REUIREMENTS Continued e.Atleastonceper18monthsby:1.Verifying thatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan6inchesWaterGaugewhileoperating theventilation systemataflowrateof6000cfmplusorminus10%.2.a.Verifying thatonaSafetyInjection SignalfromUnit1,thesystemautomatically operatesinthepressurization/cleanup mode.&b.Verifying thatonaSafetyInjection SignalfromUnit2,thesystemautomatically operatesinthepressurization/cleanup mode.3.Verifying thatthesystemmaintains thecontrolroomatapositivepressureofgreaterthanorequalto1/16inchW.G.relativetotheoutsideatmosphere atasystemflowrateof6000cfm'plusorminus10%.Aftereachcompleteorpartialreplacement ofaHEPAfilterbankbyverifying thattheHEPAfilterbanksremovegreaterthanorequalto99%oftheDOPwhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.Aftereachcompleteorpartialreplacement ofacharcoaladsorberbankbyverifying thatthecharcoaladsorbers removegreaterthanorequalto99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.plieable.
6.0      ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF            UALIFICATIONS 6.3.1    Each member    of the facility staff sh a ll meet or exceed!he minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (I) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must hetthuntmuohct                      .crater Lt      specified in Section 6.2.2P.
COOKNUCLEARPLANT-UNIT 2Page3/47-16aAMENDMENT
6.4 TRAINING 6.4.1   A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
&,434,488,202 3/4.77SNUBBERSIHITINCCONDITION FOROPATION3.7.7.1Allsafety-related snubbersshallbeOP~~"LZ.systemsrequiredOPERABLEinthoseMODES).~CTlaPithoneormoresnubbex's inoperable, within72hoursx'eplaceorrestoretheinoperable snubber(s) toOPERABLEstatusandperformanengineering evaluation perSpecification 4.7.7.1.c onthesupported component ordeclarethesupported systeminoperable andfollowtheappropriate ACTIONstatement forthatsystem.SURVELNCREUIRNTS~C4.7.7.1Eachsnubbershallbedemonstrated OP~~LEbyperformance ofthefollowing augmented inservice inspection programandtherequirements ofSpecification 4.0.5.aVisualnsectioSnubbersarecategorized asinaccessible oraccessible duringreactoroperation.
6.5 REVIEW AND AUDIT 6.5.1   PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1            The PNSRC shall function to advise the Site Vice President/Plant Manager, or designe", on all matters related to nuclear safety.
Eachofthesecategories (inaccessible andaccessible) maybeinspected independently according tothescheduledetermined byTable3.7-9.Thevisualinspection intervalforeachtypeofsnubbershallbedetermined baseduponthecriteriaprovidedinTable3.7-9andthefirstinspection intervaldetermined usingthiscriteriashallbebaseduponthepreviousinspection intervalasestablished bytherequirements ineffectbeforeAmendment No.~.b.VisualInsectionAccetanceCriteriaVisualinspections shallverify(1)thattherearenovisibleindications ofdamageorimpairedOPERABILITY, (2)attachments tothefoundation orsupporting structure aresecure,and(3)inthoselocations wheresnubbermovementcanbemanuallyinducedwithoutdisconnecting thesnubber,thatthesnubberhasfreedomofmovementandisnotfrozenup.'Snubbers whichappearinoperable as'resultofvisualinspections shallbeclassified asunacceptable andmaybereclassified asacceptable forthepurposeofestablishing thenextvisualinspection interval,"
COMPOSITION 6.5.1.2          The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Tcchnical Support, Licensing, Maintenance and Radiation Protection.
providing that(1)thecauseoftherejection isclearlyestablished andremediedforthatCOOKNUCLEARPLANT-UNIT23/47-20AMENDMENT NO.492,~&#x17d;-,~159 ELECTRICAL POUTERSYSTEHSSHUTDOWNLIHITINCCONDTIQNFOROPERAION3.8.1.2Asaminimum,thefollowing A.C.electrical powersourcessnail'oeOPERABI-'ne circuitbetweentheoffsitetransmission networkandtheonsiteClass1Edistribution system,andb.Onedieselgenerator with:1.Adayfueltankcontaining amintuaunof70gallonsoffuel,2.Afuel'storagesystemcontaining aminimumindicated volumeof46,000gallonsoffuel,and3.Afueltransferpump.ACTIONPithlessthantheaboveminimumrequiredA.C.electrical power"sources
The PNSRC membership shall consist of at least one individual from each of the areas designated.
: OPERABLE, suspendalloperations involving COREALTERATIONS orpositive-reactivity changes+untiltheminimumrequiredA.C.electrical powersourcesarerestoredtoOPENABLEstatus.SURVEIL'LANCE REUIEHENTS4.8.1.2TheaboverequiredA.C.electrical powersourcesshallbedemonstrated OPERABLEbytheperformance ofeachoftheSurveillance Requirements of4.8.1.1.1 and4.8.1.1.2 exceptforrequirement 4.8.1.1.2.a.5.
All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.
f*Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRUSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior opeiator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
TheCOOKNUCL:"MPLANT-UNIT23/48-9AHENDHENT NO.4M,Ma.159
COOK NUCLEAR PLANT-UNIT2                                  Page 6-4                 AMENDMENT34, 447) 438,       4VR, 47$ , 197
~p 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8'LECTRICAL POWERSYSTEMSSURVEILLANCE REUIREMENTS Continued tb.Atleastonceper92daysbyverifying that:1.Thevoltageofeachconnected cellisgreaterthanorequalto2.13voltsunderfloatcharge.Thespecificgravity,corrected to/7'F,andfullelectrolyte level(fluid'tthebottomofthemaximumlevelindication mark),ofeachconnected cellisgreaterthanorequalto1.200andhasnotdecreased morethan0.03fromthevalueobservedduringtheprevioustest,and3.Theelectrolyte levelofeachconnected cellisbetweenthetopoftheminimumlevelindication markandthebottomofthemaximumlevelindication mark.Atleastonceper1&monthsbyverifying that:1.Thecells,cellplatesandbatteryracksshownovisualindication ofphysicaldamageorabnormaldeterioration, Thecell-to~ll andterminalconnections areclean,tight,freeofcorrosion andcoatedwithanti-corrosion
: material, f3.Thebatterychargerwillsupplyatleast140amperesatgreaterthanorequalto250voltsforatleast4hours.Atleastonceper18months,performabatteryservicetestduringshutdown(MODES5or6),byverifying thatthebatterycapacityisadequatetosupplyandmaintaininOPERABLEstatustheactualorsimulated emergency loadsforthedesigndutycyclewhichisbasedonthecomposite loadprofile.Thecomposite loadprofileenvelopes boththeLOCA/LOOP andStationBlackoutprofilesandprovidesthebasisforthetimeslistedinTable4.8-2.Thebatterychargerwillbedisconnected throughout thetest.Thebatteryterminalvoltageshallbemaintained greaterthanorequalto210voltsthroughout thistest~Atleastonceper60months,conductaperformance testofbatterycapacityduringshutdown(MODES5or6),byverifying thatthebatterycapacityisatleast80%ofthemanufacturer's rating.Whenthistestisperformed inplaceofabatteryservicetest,amodifiedperformance testshallbeconducted.
Annualperformance testsofbatterycapacityshallbegiventoanybatterythatshowssignsofdegradation orhasreached85%oftheservicelifeexpectedfortheapplication.
Degradation isindicated whenthebatterycapacitydropsmorcthan10%fromitscapacityonthepreviousperformance test,orisbelow90%ofthemanufacturer's rating.Ifthebaueryhasreached85%ofservicelife,deliversacapacityof100%orgreaterofthemanufacturer's ratedcapacity, andhasshownnosignsofdegradation, performance testingattwoyearintervals isacceptable untilthebatteryshowssignsofdegradation.
Mte-provisions-ef-Specif catialicableCOOKNUCLEARPLANT-UNIT 2Page3/48-13AMENDME<NT 443,439,4@i,183 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSD.C.DISTRIBUTION
-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.2.4Asaminimum,thefollowing D.C.electrical equipment andbusshallbeenergized andOPERABLE:
1-250-voltD.C.bus,and1-250-voltbatterybankandchargerassociated withtheaboveD.C.bus.APPLICABILITY:
MODES5and6.ACTION:Withlessthantheabovecomplement ofD.C.equipment andbusOPERABLE, establish CONTAINMENT INTEGRITY within8hours.SURVEILLANCE REUIREMENTS 4.8.2.4.1 Theaboverequired250-voltD.C.busshallbedetermined OPERABLEandenergized atleastonceper7daysbyverifying correctbreakeralignment andindicated poweravailability.
4.8.2.4.2 Theaboverequired250-voltbatterybankandchargershallbedemonstrated OPERABLEperSurveillance Requirement 4.8.2.3.2.~
COOKNUCLEARPLANT-UNIT 2Page3/48-15e-epplieabl
+242X2.cLfowho4-C~wtte~~+dtargcr.
ttirtnncnt AMENDMENT 443,4',183 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.
wheneverirradiated fuelisinthestoragepool.Pithnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepooluntilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.*b.Theprovisions ofSpecifications 3.0.3and3.0'arenotapplicable.
S'RVVCRUITS4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:
a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying
-hatthetrainoperatesforatleast15minutes.b.Atleastonceper18monthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following
: painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.,C.COOK-UNIT23/49-12Amendment No1112.Verifying thatthecharcoaladsorbers remove)99%ofahalogenated hydrocarbon
-,refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflawrateof30,000cfm+10%.gillieQALac4%clqqrog~clvxllI+Thecranebayroll-updoorandthemaybeopenedunderadministrative control.duringmovementoffuelwithinthestoragepoolorcrane.operation withloadsoverthestoragepool.SharedsystemwithD.C.COOK-UNIT1.Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adeenergized mainloadblockneednotbeconsidered aload.
5.0DESIGNFEATURES5.6FUELSTORAGEContinued CRITICALITY
-SPENTFUELContinued Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations'an~mphieai~ieted=in=Rgtt~~
ForReion2StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,260E+149EForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E2+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2FuelstoredinthespentfuelstorageraCksshallhaveanominalfuelassemblyenrichment asfollows:Description MaximumNominalFuelAssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.954.954.95COOKNUCLEARPLANT-UNIT 2Page54AMENDMENT 44,424,447,4',198
'3r'94~C~ZCCCruporpxi~ccBUrc%lPL"=MAN2LosI(tl~EiA~~f.4.14LOLSLOA+A44.~IN~i.BlRlCHMKHT,
%U-2355-8


==6.0 ADMINISTRATIVE==
ATTACHMENT 3A TO AEP:NRC:0433Q PROPOSED TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 1 3/4 0"3 3/4 3-2la 3/4 4-38 3/4 4-40 3/4 7-15 3/4 9-1 3/4 9-13 5-6 5-7b 6-4
CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilitystaffshallmeetorexceed!he minimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(I)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomusthetthuntmuohct
'.craterLtspecified inSection6.2.2P.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesigne",
onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.
Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Tcchnical Support,Licensing, Maintenance andRadiation Protection.
ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.
Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.
Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioropeiatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.
COOKNUCLEARPLANT-UNIT 2Page6-4AMENDMENT 34,447)438,4VR,47$,197


ATTACHMENT 3ATOAEP:NRC:0433Q PROPOSEDTECHNICAL SPECIFICATIONS PAGESREVISEDPAGESUNIT13/40"33/43-2la3/44-383/44-403/47-153/49-13/49-135-65-7b6-4 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REQUIREMENTS Surveillance intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASMEBoilerandPressureVesselCodeandapplicable Addendaterminology forinservice insctionandtestincriteriaWeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monthsYearlyorannuallyRequiredfrequencies forperforming inservice inspection andtestingactivities Atleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysTheprovisions ofSpecification
ASME Boiler and Pressure Vessel Code and              Required frequencies for performing applicable Addenda terminology for                    inservice inspection and testing activities inservice ins ction and testin criteria Weekly                            At least once  per 7 days Monthly                            At least once  per 31 days Quarterly or every 3 months                  At least once  per 92 days Semiannually or every 6 months                At least once  per 184 days Yearly or annually                      At least once  per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies              for performing inservice inspection and testing activities.
Performance of the above'inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede                the requirements of any Technical Specification.
4.0.6        Deleted.
4.0.7        Deleted.
COOK NUCLEAR PLANT-UNIT1                        Page 3/4 0-3                      AMENDMENT400, 43k, 444


==4.0. 2areapplicable==
1 f
totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.
U ~
Performance oftheabove'inservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.
    <t
NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.
4.0.64.0.7Deleted.Deleted.COOKNUCLEARPLANT-UNIT 1Page3/40-3AMENDMENT 400,43k,444 1U~f<t 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMIi22'I'ATION ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT6.MOTORDRIVENAUXILIARY FEEDWATER PUMPSCa.SteamGenerator Water3/Stm.Gen.Level-Low-Low 141,2,32/Stm.Gen.2/Stm.Gen.anyStm.Gen.MINIMUMTOTALNO.OFCHANNELSCHANNELSAPPLICABLE CHANNELSTOTRIPOPERABLEMODESACTIONb.4kvBusLossofVoltage3/BusPumpStartValveActuation (Bothtrains)c.SafetyInjection 2/bus(T11A-TrainB;T11D-TrainA)2/buson(T11A&T11Bor2/bussesT11C&T11D)1,2,31,2,31418'.LossofMainFeedwater Pumps7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPS'21,218a.SteamGenerator Water3/Stm.Gen.Level-Low-Low b.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOFPOWER2/Stm.Gen.2/Stm.Gen.any2Stm.Gen.I,2,31,2,31419a.4kvBusLossofVoltage1,2,3,414b.4kvBusDegradedVoltage3/Bus(TIIA-TrainB;TIID-TrainA)2/Bus2/Bus1,2,3,4(T11A-Train B;(T11A-Train B;T11D-Train A)T11D-Train A)14COOKNUCLEARPLANT-UNIT 1Page3/43-21nAMENDMENT
$9,48$,4' I
3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMREACTORVESSELHEADVENTSSURVEILLANCE REUIREMENTS 4.4.12.1BothReactorVesselheadventpathsshallbedemonstrated OPERABLEatleastoncepert8monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.
CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.Verifying flowthroughbothoftheReactorVesselheadventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 1Page3/44-38AMENDMENT 98 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMPRESSURIZER STEAMSPACEVENTSSURVEILLANCE REUIREMENTS 4.4.12.2BothPressnrlacr steamspaceventpathsshallbedemonstrated OPERABLEatleastoncepert8monthsby:1.Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.
CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT IPage3/4440AMENDMENT 98 3/4LIMITINGCONDITIONS IOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.7PLANTSYSTEMSPLANTSYSTEMS3/4.7.3COMPONENT COOLINGWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.3.1APPLICABILITY:
ACTION:Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.
Atleastonecomponent coolingwaterflowpathinsupportofUnit2shutdownfunctions shallbeavailable.
Specification 3.7.3.1.a-MODES1,2,3and4.Specification3.7.3.1.b-AtalltimeswhenUnit2isinMODES1,2,3,or4.WhenSpeciiflication3.7.3.1.a isapplicable:
Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification3.7.3.1.b isapplicable:
WithnoflowpathtoUnit2available, returnatleastoneflowpathtoavailable statuswithin7days,orprovideequivalent shutdowncapability inUnit2andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit2inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirementsof Specification3.0.4 arenotapplicable.
SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:
Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.Byverifying pumpperformancepursuant toSpeciftcation4.0.5.
Atleastonceperidmonthsduringshutdown, byverifying thattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.
COOK'NUCLEAR PLANT-UNIT 1Page3/47-15dhggbtDhtgbyg gttg,ggh,ddd,ddd r>0 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.9REFUELING OPERATIONS BORONCONCENTRATION LIMITINGCONDITION FOROPERATION 3.9.1Withthereactorvesselheadunboltedorremoved,theboronconcentration ofallfilledportionsoftheReactorCoolantSystemandtherefueling canalshallbemaintained uniformandsufficient toensurethatthemorerestrictive ofthefollowing reactivity conditions ismet:EitheraK,of0.95orless,whichincludesa1%Ak/kconservative allowance foruncertainties, orAboronconcentration ofgreaterthanorequalto2400ppm,whLhincludesa50ppmconservative allowance foruncertainties.
APPLICABILITY:
ACTION:MODE6Withtherequirements oftheabovespecification notsatisfied, immediately suspendalloperations involving COREALTERATIONS orpositivereactivity changes"andinitiateandcontinueborationatgreaterthanorequalto10gpmof20,000ppmboricacidsolutionoritsequivalent untilK,zisreducedtolessthanorequalto0.95ortheboronconcentration isrestoredtogreaterthanorequalto2400ppm,whichever isthemorerestrictive.
Theprovisions ofSpecification3.0.3 arenotapplicable.
SURVEILLANCE REUIREMENTS 4.9.1.1Themorerestrictive oftheabovetworeactivity conditions shallbedetermined priorto:a.Removingorunbolting thereactorvesselhead,andb.Withdrawal ofanyfulllengthcontrolrodinexcessof3feetfromitsfullyinsertedposition.
4.9.1.2Theboronconcentration ofthereactorcoolantsystemandtherefueling, canalshallbedetermined bychemicalanalysisatleastonceper72hours.'Thereactorshallbemaintained inMODE6whenthereactorvesselheadisunboltedorremoved.10Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.
COOKNUCLEARPLANT-UNIT 1Page3/49-1AMENDMENTS%
II~~IC4kAt"t'I,K 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMIPlTS 3/4.9REFUELING OPERATIONS REFUELING OPERATIONS STORAGEPOOLVENTILATION SYSTEMh*LIMITINGCONDITION FOROPERATION 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.
APPLICABILITY:
Wheneverirradiated fuelisinthestoragepool.ACTION:a.Withnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool+untilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.'h b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:
Atleastonceper31daysbyinitiating fiowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.Atleastonceper18monthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following
: painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove299%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfmk10%.srthecranebayroti-updoorandthesouthdooroytheauxiliary buildingcranebaymaybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool.'pd'Shared systemwithD.C.COOK-UNIT2.+Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adewnergized mainloadblockneednotbeconsidered aload.COOKNUCLEARPLANT-UNIT 1Page3/49-13 u'tllI'I'ras~>>'+'.,>>.r 5.0DESIGNFEATURES5.6FUELSTORAGEContinued 1.Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wt%U-235,orspentfuelregardless ofthedischarge fuelburnup.Region2isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast50,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.
Region3isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast38,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.
Theequivalent reacdvtqr criteriaforRegion2andRegion3isdefinedviathefollowing equations:
ForReion2Stora eMinimumAssemblyAverageBurnupinMWD/MTU=22670+22220E-2260'+149EForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E~+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2:IFuelstoredinthespentfuelstorageracksshallhaveamaximumnominalfuelassemblyenrichment asfollows:MaximumNominalFuelDescription AssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17VS17x174.954.954.954.95COOKNUCLEARPLANT-UNIT 1Page54AMENDMENT 5V,486,448,469,SH t~'~~~I'~<<')i~4vl(Lh4'4IIIl,qyg Figure5.6-3intentionally deleted.COOKNUCLEARPLANT-UNlT 1Page5-7bAMENDMENT Bi9.


==6.0 ADMINISTRATIVE==
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3    INSTRUMIi22'I'ATION ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF      CHANNELS      CHANNELS        APPLICABLE FUNCTIONALUNIT                CHANNELS          TO TRIP        OPERABLE          MODES    ACTION
CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilitystaffshallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustbequalified asspecified inSection6.2.2.g.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITI'EE NSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.
: 6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS C
Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Tcchnical Support,Licensing, Maintenance andRadiation Protection.
: a. Steam Generator Water 3/Stm. Gen.        2/Stm. Gen. 2/Stm. Gen.         1,2,3      14 Level-Low-Low                            any Stm.Gen.
ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.
: b. 4 kv Bus Loss  of Voltage                3/Bus                                                1,2,3      14 Pump Start                              2/bus (T11A-Train B; T11D-Train A)
Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 Section4.4forcomparable positions.
Valve Actuation (Both                    2/bus on (T11A trains)                                  & T11B or 2/busses T11C
Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge.
                                                & T11D)
atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.
: c. Safety Injection                                                            1, 2, 3   18'.
COOKNUCLEARPLANT-UNIT 1Page64AMENDMENT 49,6S,4',484)486,493,212
Loss of Main          '2                                                      1,2     18 Feedwater Pumps
: 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
: a. Steam Generator Water 3/Stm. Gen.         2/Stm. Gen. 2/Stm. Gen.         I, 2, 3    14 Level-Low-Low                            any 2 Stm.
Gen.
: b. Reactor Coolant Pump    4-1/Bus                                              1,2,3      19 Bus Undervoltage
: 8. LOSS OF POWER
: a. 4 kv Bus Loss  of                                                          1,2,3,4      14 Voltage
: b. 4 kv Bus Degraded      3/Bus            2/Bus          2/Bus            1, 2, 3, 4  14 Voltage                (TI IA-Train B;  (T11A-Train B; (T11A-Train B; TI ID-Train A)    T11D-Train A)  T11D-Train A)
COOK NUCLEAR PLANT-UNIT1                      Page 3/4 3-21n                  AMENDMENT$ 9, 48$ , 4'


ATTACHMENT 3BTOAEP:NRC:0433Q PROPOSEDTECHNICAL SPECIFICATIONS PAGESREVISEDPAGESUNIT2,3/40-33/40-43/43-113/43-203/43-303/43-313/43-343/43-44d3/43-473/44-133/44-143/44-333/44-353/4,4-373/45-43/45"83/46-123/46-143/46-473/47-123/47-133/47-16a3/47-203/48-93/48-133/48-153/49-125-65-86-4 3/4LIMITINGCONDITIONS FOROPERATION ANDSIRVEILLANCE REQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REUIREMENTS b.Surveillance Intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:
I 3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4   REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM REACTOR VESSEL HEAD VENTS SURVEILLANCERE UIREMENTS 4.4.12.1      Both Reactor Vessel head vent paths shall be demonstrated    OPERABLE at least once per t8 months by:
ASMEBoilerandPressureVesselCodeandapplicable Addendaterminology forinservice inspection andtestingcriteriaWeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monothsYearlyorannuallyRequiredfrequencies forperforming inservice inspection andtestingactivities Atleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysc.Theprovisions ofSpecification
Verifying the common manual isolation valve in the Reactor vessel head vent is sealed in the open position.
Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
Verifying flow through both of the Reactor Vessel head vent paths during venting operation, while in Modes 5 or 6.
COOK NUCLEAR PLANT-UNIT1                                Page 3/4 4-38                    AMENDMENT98


==4.0. 2areapplicable==
3/4     LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,4   REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS SURVEILLANCE RE UIREMENTS 4.4.12.2       Both Pressnrlacr steam space vent paths shall be demonstrated OPERABLE at least once per t8 months by:
totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.
: 1.     Verifying the common manual isolation valve in the Pressurizer steam space vent is sealed in the open position.
Performance oftheaboveinservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.
Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.
: 3.     Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.
4.0.6Deleted.4.0.7Deleted.COOKNUCLEARPLANT-UNIT 2Page3/40-3AMENDMENT VS,QV,48k 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REUIREMENTS 4.0.8Deleted.4.0.9Deleted.COOKNUCLEARPLANT-UNIT2 1Page3/4S4~wuMHmm,m TABLE4.3-1REACTORTRIPSYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNIT1.ManualReactorTripA.ShuntTripFunctionB.Undervoltage TripFunction2.PowerRange,NeutronFlux3.PowerRange,NeutronFlux,HighPositiveRate4.PowerRange,NeutronFlux,HighNegativeRate5.Intermediate Range,NeutronFlux6.SourceRange,NeutronFlux7.Overtemperature b,T8.Overpower hT9.Pressurizer Pressure-Low10.Pressurizer Pressure-High11.Pressurizer WaterLevel-High12.LossofFlow-Single LoopCHANNELCHECKN.A.N.A.SN.A.CHANNELCALIBRATION N.A.N.A.D(2,8),M(3,8)andQ(6,8)R(6)R(6)R(6,8)R(6,14)R(9)R(9)R(8)CHANNELFUNCTIONAL TESTS/U(1)(10)
COOK NUCLEAR PLANT-UNITI                                Page 3/4 440                        AMENDMENT98
S/U(1)(10)
MandS/U(1)S/U(1)M(14)GildS/U(1)MMMODEINWHICHSURVEILLANCE REUIREDI,2,3,4,51,2,3,4',51,2and1,21,21,2,and2(7),3(7),4and51,21,21,21,21,2 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.3-3Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPSMINIMUMTOTALNO.CHANNELSCHANNELSOFCHANNELSTOTRIPOPERABLEAPPLICABLE MODESACTIONa.SteamGenerator Water3/Stm.Gen.Level-Low-Low2/Stm.Gen.2/Stm.Gen.any2Stm.Gen.1,2,314'.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOF'POWER1,2,319'.4kVBusLossofVoltageb.4kVBusDegradedVoltage9.MANUALa.SafetyInjection (ECCS)Feedwater Isolation ReactorTrip(SI)Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation Auxiliary Feedwater PumpsEssential ServiceWaterSystemb.Containment SprayContainment Isolation-Phase"B"Containment PurgeandExhaustIsolation Containment AirRecirculation Fanc.Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation d.SteamLineIsolation 3/Bus3/BusP21A-Train8;T21D-TninA)2/train1/train1/train2/steamline(1pertrain)2/Bus(T21A-Tnin8;TZID-Train A)1/train1/train1/train2/steamline(1pertrain)2/Bus2/Bus(TRIA-Tnin B;T21D-Tnin A)2/train1/train1/train2/operating steamline(1pertrain)1,2,3,414',2,3,4 141,2,3,4181,2,3,4181,2,3,4181,2,320COOKNUCLEARPLANT-UNIT 2Page3/43-20AMENDMENT VV;4%,437 3/4LIMlTINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCFIONAL UNITl.SAFETYINJECTION, TURBINETRIP,FEEDWATER ISOLATION, ANDMOTORDRIVENAUXILIARY FEEDWATER PUMPSTRIPACTUATING DEVICEOPERATIONAL MODESINCHANNELWHICHCHANNELCHANNELFUNCTIONAL SURVEILLANCE CHECKCALIBRATION TEST~RE(EUIRED a.ManualInitiation b.Automatic Actuation Logicc.Containment Pressure-Highd.Pressurizer Pressure-Lowe.Differential PressureBetweenSteamLines-Highf.SteamLincPressure-LowN.A.M(3)N.A.N.A.N.A.N.A.SecFunctional Unit9M(2)N.A.I,2,3,4I,2,3I,2,3I,2,3I,2,32.CONTAINMENT SPRAYa.ManualInitiation b.Automatic Actuation Logicc.Containment Pressurc-High-High 3.CONTAINMENT ISOLATION a.PhaseAIsolation I)Manual2)FromSafetyInjection Automatic Actuation Logicb.PhaseBIsolation I)Manual2)Automatic Actuation Logic3)Containment Pressure-High-HighN.A.N.A.N.A.N.A.N.A.SeeFunctional Unit9M(2)M(3)SecFunctional Unit9M(2)SeeFunctional Unit9M(2)M(3)N.A.N.A.N.A.N.A.N.A.I,2,3,4I,2,3I,2,3,4I,2,3,4I,2,3COOKNUCLEARPLANT-UNlT 2Page3/43-30AMENDMENT 84,9,43V,488 g~tb0II 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNITc.PurgeandExhaustIsolation CHANNELCHECKCHANNELCALIBRATION CHANNELFUNCfIONAL TESTTRIPACTUATING DEVICEOPERATIONAL MODESINWHICHSURVEILLANCE RHtHUIRED I)Manual2)Containment Radioactivity
-HighSeeFunctional Unit9eN.A.I,2,3,44.STEAMLINEISOLATION a.Manualb.Automatic Actuation Logicc.Containment Pressure-High-High d.SteamHowinTwoSteamLines-HighCoincident withT~-Low-Lowc.SteamLinePressure-LowN.A.N.A.SeeFunctional Unit9M(2)M(3)MN.A.N.A.N.A.N.A.I,2,31,2,31,2,31,2,35.TURBINETRIPANDFEEDWATER ISOLATION a.SteamGenerator WaterLcvcl-High-High MN.A.1,2,36.MOTORDRIVENAUXILIARY FEEDWATER PUMPSa.SteamGenerator WaterLevel-Low-Lowb.4kVBusLossofVoltageSc.SafetyInjection N.A.d.LossofMainFeedPumpsN.A.RN.A.N.A.MM(2)RN.A.N.A.N.A.N.A.1,2,31,2,3I,2,31,2COOKNUCLEARPLANT-UNIT2 Page3/43-31AMENDMENT%,
%,43k,434,4&V,
~)~/,~
3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,3INFIRUMENTATION INSTRUMENTATION 3/4.3.3MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITINGCONDITION FOROPERATION 3.3.3.1Theradiation monitoring instrumentation channelsshowninTable3.3-6shallbeOPERABLEwiththeiralarm/trip setpoints withinthespecified limits.APPLICABILITY:
ACTION:AsshowninTable3.3-6.b.Witharadiation monitoring channelalarm/trip setpointexceeding thevalueshowninTable3.3-6,adjustthesetpointtowithinthelimitwithin4hoursordeclarethechannelinoperable.
Withoneormoreradiation monitoring channelsinoperable, taketheACTIONshowninTable3.3-6.c.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable SURVEILLANCE REUIREMENTS 4.3.3.1Eachradiation monitoring instrumentation channelshallbedemonstrated OPERABLEbytheperformance oftheCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESToperations duringthemodesandatthefrequencies showninTable4.3-3.COOKNUCLEARPLANT-UNIT 2Page3/43-34 TABLE4.3-6AAPPENDIXRREMOTESHUTDOWNMONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS 00RCORIRtA4JC4INSTRUMENT 1.SteamGenerators 1and4Level2.SteamGenerators 2and3Level3.SteamGenerators 1and4Pressure4.SteamGenerators 2and3Pressure5.ReactorCoolantLoop4Temperature (Cold)6.ReactorCoolantLoop4Temperature (Hot)7.ReactorCoolantLoop2Temperature (Cold)ReactorCoolantLoop2Temperature (Hot)9.Pressurizer Level10.ReactorCoolantSystemPressure11.ChargingCross-Flow BetweenUnits12.SourceRangeNeutronDetector(N-23)LOCATIONLSICabinet1andLSICabinet4LSICabinet2andLSICabinet4LSICabinet4andLSICabinet5LSICabinet4andLSICabinet6LSICabinet4andLSICabinet5LSICabinet4andLSICabinet5LSICabinet4andLSICabinet6LSICabinet4andLSICabinet6,LSICabinet3LSICabinet3CorridorElev.587'SICabinet4CHANNELCHECKMCHANNELCALIBRATION
,R*Charging Cross-Flow betweenUnitsisaninstrument commontobothUnitIand2.Thissurveillance willonlybeconducted onanintervalconsistent withUnitIrefueling.


TABLE4.3-10POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS INSTRUMENT CHANNELCHECKCHANNELCALIBRATION 1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.Containment PressureReactorCoolantOutletTemperature
3/4      LIMITINGCONDITIONS I OR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7    PLANT SYSTEMS PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.
-Tnor(WideRange)ReactorCoolantInletTemperature
At least one component cooling water flowpath in support of Unit 2 shutdown functions shall be available.
-Tco~(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevelSteamLinePressureSteamGenerator WaterLevel-NarrowRangeRWSTWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator
APPLICABILITY:              Specification 3.7.3.1.a- MODES 1, 2, 3 and 4.
-LimitSwitchesPORVBlockValvePositionIndicator
Specification3.7.3.1.b- At all times when Unit 2 is in MODES 1, 2, 3, or 4.
-LimitSwitchesSafetyValvePositionIndicator
ACTION:
-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)
When Speciiflication3.7.3.1.a is applicable:
ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours or be in at least HOT STANDBYwithin the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
Containment SumpLevelContainment WaterLevelMMMMMMMMMMMMMMMMu~MMRRRRRRRRRRRRRRRtuRP)RRtnPartial rangechannelcalibration forsensortobeperformed belowP-12inMODE3."KithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.
When Specification3.7.3.1.b is applicable:
+Completion ofchannelcalibration forsensorstobeperformed belowP-12inMODE3.  
With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBYwithin the next 12 hours and HOT SHUTDOWN within the following 24 hours.
-001STSAMPLEINSPECTION TABLE4.4-2STEAMGENERATOR TUBEINSPECTION 2NDSAMPLEINSPECTION 3RDSAMPLEINSPECTION SampleSizeAminimumofSTubesperS.G.ResultC-1C-2ActionRequiredNonePlugdefective tubesandinspectadditional 2StubesinthisS.G.ResultN/AC-1C-2ActionRequiredN/ANonePlugdefective tubesandinspectadditional 4StubesinthisS.G.ResultN/AN/AC-1ActionRequiredN/AN/ANoneC-3InspectalltubesinthisS.G.,plugdefective tubesandinspect2StubesineachotherS.G.C-3AllotherS.G.sareC1PerformactionforC-3resultoffirstsampleNoneC-2C-3N/AN/APlugdefective tubesPerformactionforC-3resultoffirstsampleN/AN/APromptnotification toNRCpursuanttospecification 6.9.1SomeS.G.sPerformactionforC-2C-2butnoresultofsecondsampleadditional S.G.areC-3.N/AN/AAdditional S.G.isC-3InspectalltubesineachS.G.andplugdefective tubes.Promptnotification toNRCpursuanttospecification 6.9.1.'/AN/AS=3(N+n)%
The requirementsof Specification3.0.4 are not applicable.
WhereNisthenumberofsteamgenerators intheunit,andnisthenumberofsteamgenerators inspected duringaninspection.
SURVEILLANCERE UIREMENTS 4.7.3.1            At least two component cooling water loops shall be demonstrated OPERABLE:
IIh 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGELEAKAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1Thefollowing ReactorCoolantSystemleakagedetection systemsshallbeOPERABLE:
At  least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
a1APPLICABILITY:
At  least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.
Oneofthecontainment atmosphere particulate radioactivity monitoring channels(ERS-2301orERS-2401),
By verifying pump performancepursuant to Speciftcation4.0.5.
Thecontainment sumplevelandflowmonitoring system,andEitherthecontainment humiditymonitororoneofthecontainment atmosphere gaseousradioactivity monitoring channels(ERS-2305 orERS-2405).
At least once per id months during shutdown, by verifying that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.
MODES1,2,3and4ACTION:Withonlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation maycontinueforupto30daysprovidedgrabsamplesofthecontainment atmosphere areobtainedandanalyzedatleastonceper24hourswhentherequiredgaseousand/orparticulate radioactivity monitoring channelsareinoperable; otherwise, beinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonstrated OPERABLEby:Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-performance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3.Containment sumplevelandflowmonitoring system-perfo'rmance ofCHANNELCALIBRATION atleastonceper18months.C.Containment humiditymonitor(ifbeingused)-performance ofCHANNELCALIBRATION atleastonceper18months.COOKNUCLEARPLANT-UNIT 2Page3/44-14AMENDMENT V8,43k,459 II1>i~C5PI 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION Continued WithPORVsandblockvalvesnotinthesamelineinoperable duetocausesotherthanexcessive seatleakage,within1hourrestorethevalvestoOPERABLEstatusorcloseandde-energize theassociated blockvalveandplacetheassociated PORVinmanualcontrolineachrespective line.ApplytheportionsofACTIONcordabove,relatingtotheOPERATIONAL MODE,asappropriate fortwoorthreelinesunavailable.
COOK'NUCLEAR PLANT-UNIT1                              Page 3/4 7-15                dhggbtDhtgbyg gttg, ggh, ddd, ddd
h.Theprovisions ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.4.1F1Inadditiontotherequirements ofSpecification 4.0.5,eachPORVshallbedemonstrated OPERABLE:
a.Atleastonceper31daysbyperformance ofaCHANNELFUNCTIONAL TEST,excluding valveoperation, andb.Atleastonceper18monthsbyoperating thePORVthroughonecompletecycleoffulltravelduringMODES3or4,andc.Atleastonceper18monthsbyoperating solenoidaircontrolvalvesandcheckvalvesinPORVcontrolsystemsthroughonecompletecycleoffulltravel,andd.Atleastonceper18monthsbyperforming aCHANNELCALIBRATION oftheactuation instrumentation.
4.4.11.2Eachblockvalveshallbedemonstrated OPERABLEatleastonceper92daysbyoperating thevalvethroughonecompletecycleoffulltravelunlesstheblockvalveisclosedinordertomeettherequirements ofACTIONb,c,ordinSpecification 3.4.11.4.4.11.3Deleted.COOKNUCLEARPLANT-UNIT 2Page3/44-33AMENDMENT 45k)458,459,46k,496
~~w8'IllI00,t~+il~p"/'qI'r',ii'I'9 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEM"'EACTORVESSELHEADVENTSSURVEILLANCE REUIREMENTS 4.4.12.1BothReactorVesselheadventpathsshallbedemonstrated OPERABLEatleastonceper18monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.
CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.Verifying flowthroughbothoftheReactorVesselheadventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 2Page3/44-35AMENDMENT 65


3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMPRESSURIZER STEAMSPACEVENTSSURVEILLANCE REUIREMENTS 4.4.12.2BothPressurizer steamspaceventpathsshallbedemonstrated OPERABLEatleastonceper18monthsby:1.Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.
r>
2.CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 2Page3/44-37AMENDMHNT dd
0
~')F+F~<<g/<<I,F<<b~<<"<<,"P<<FY 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,5EMERGENCY CORECOOLINGSYSTEMS(ECCS)SURVEILLANCE REUIREMENTS 4.5.2EachECCSsubsystem shallbedemonstrated OPERABLE:
 
aoAtleastonceper12hoursbyverifying thatthefollowing valvesareintheindicated positions withpowertothevalveoperators removed:ValveNumberValveFunctionValvePositiona.IM0-390b.IMO-315c.IM0-325d.IM0-262'.
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.9    REFUELING OPERATIONS BORON CONCENTRATION LIMITINGCONDITIONFOR OPERATION 3.9.1    With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
IM0-263f.~IM0-261'.
Either a K,of0.95 or less, which includes    a 1%  Ak/k conservative allowance for uncertainties, or A boron concentration of greater than or equal to 2400 ppm, whLh includes      a 50 ppm conservative allowance for uncertainties.
APPLICABILITY:            MODE 6 ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONSor positive reactivity changes" and initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or its equivalent until K,z is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm, whichever is the more restrictive. The provisions of Specification3.0.3 are not applicable.
SURVEILLANCERE UIREMENTS 4.9.1.1            The more restrictive of the above two reactivity conditions shall be determined prior to:
: a.      Removing or unbolting the reactor vessel head, and
: b.      Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position.
4.9.1.2            The boron concentration of the reactor coolant system and the refueling, canal shall be determined by chemical analysis at least once per 72 hours.
'The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.
10 For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.
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II ~
    ~
I C 4    k    A t" t'
                    ,K I
 
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMIPlTS 3/4.9    REFUELING OPERATIONS REFUELING OPERATIONS STORAGE POOL VENTILATIONSYSTEMh*
LIMITINGCONDITION FOR OPERATION 3.9.12           The spent fuel storage pool exhaust ventilation system shall be OPERABLE.
APPLICABILITY:              Whenever irradiated fuel is in the storage pool.
ACTION:
: a.      With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool+ until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.'h
: b.      The provisions    of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCERE UIREMENTS 4.9.12            The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:
At least once per    31 days by initiating  fiow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.
At least  once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
: 1.         Deleted.
: 2.        Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm k 10%.
srthe crane bay roti-up door and the south door oy the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.
'pd'Shared system with D. C. COOK - UNIT 2.
+This does not include the main load block. For purposes of this specification, a dewnergized main load block need not be considered a load.
COOK NUCLEAR PLANT-UNIT1                                      Page 3/4 9-13
 
u
              't ll I'
I 'r a s          ~ >>'  + '
                            ., > >.r
 
5.0      DESIGN FEATURES 5.6 FUEL STORAGE Continued
: 1.        Region 1 is designed to accommodate new fuel with a maximum nominal enrichment            of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.
Region 2 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
The equivalent reacdvtqr criteria for Region 2 and Region 3 is defined via the following equations:
For Re ion2Stora    e Minimum Assembly Average Burnup in MWD/MTU =
22670+ 22220      E-2260'+        149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU =
                                            -26,745 + 18,746    E-  1,631 E~ + 98.4 E3 Where E  = Initial Peak Enrichment I
5.6.1.2:      Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as  follows:
Maximum Nominal Fuel Description                                            Assembly Enrichment Wt. % U-235
: 1)      Westinghouse                15 x 15 STD                        4.95 15 x 15 OFA
: 2)        Exxon/ANF                    15x15                              4.95
: 3)        Westinghouse                17 x 17 STD                        4.95 17x 17OFA 17 x 17 VS
: 4)        Exxon/ANF                    17 x 17                            4.95 COOK NUCLEAR PLANT-UNIT1                                  Page  54          AMENDMENT5V, 486, 448, 469, SH
 
t
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    ~
    ~
      ~ ~
      <<')i~ 4 Iv ' l (
Lh 4 '4 III l, q yg
 
Figure 5.6-3 intentionally deleted.
COOK NUCLEAR PLANT-UNlT1            Page 5-7b              AMENDMENTBi9.
 
6.0    ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF          UALIFICATIONS 6.3.1  Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must be qualified as specified in Section 6.2.2.g.
6.4 TRAINING 6.4.1  A retraining and replacement training program for the facility staff shall be maintained under the direction  of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5              of ANSI N18. 1-1971 and 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITI'EE                        NSRC FUNCTION 6.5.1.1          The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.
COMPOSITION 6.5.1.2          The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Tcchnical Support, Licensing, Maintenance and Radiation Protection.
The PNSRC membership shall consist of at least one individual from each of the areas designated.
All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge. at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
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ATTACHMENT 3B TO AEP:NRC:0433Q PROPOSED  TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 2
                , 3/4  0-3 3/4  0-4 3/4  3-11 3/4  3-20 3/4  3-30 3/4  3-31 3/4  3-34 3/4  3-44d 3/4  3-47 3/4  4-13 3/4  4-14 3/4  4-33 3/4  4-35 3/4,4-37 3/4  5-4 3/4  5"8 3/4  6-12 3/4  6-14 3/4  6-47 3/4  7-12 3/4  7-13 3/4  7-16a 3/4  7-20 3/4  8-9 3/4  8-13 3/4  8-15 3/4  9-12 5-6 5-8 6-4
 
3/4  LIMITINGCONDITIONS FOR OPERATION AND SIRVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCERE UIREMENTS
: b.      Surveillance Intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and              Required frequencies for performing applicable Addenda terminology for                    inservice inspection and testing activities inservice inspection and testing criteria Weekly                            At least once per 7 days Monthly                            At least once per 31 days Quarterly or every 3 months                  At least once per  92 days Semiannually or every 6 monoths                At least once per  184 days Yearly or annually                      At least once per 366 days
: c.      The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
4.0.6 Deleted.
4.0.7 Deleted.
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3/4  LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCERE UIREMENTS 4.0.8 Deleted.
4.0.9 Deleted.
COOK NUCLEAR PLANT-UNIT2 1
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TABLE4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATIONSURVEILLANCERE UIREMENTS CHANNEL      MODE IN WHICH CHANNEL      CHANNEL      FUNCTIONAL      SURVEILLANCE FUNCTIONALUNIT                                    CHECK    CALIBRATION        TEST            RE UIRED
: 1. Manual Reactor Trip A. Shunt Trip Function                          N.A.            N.A.      S/U(1)(10)  I, 2, 3, 4,  5 B. Undervoltage Trip Function                  N.A.            N.A.      S/U(1)(10)  1,2,  3,4',5
: 2. Power Range, Neutron Flux                        S        D(2,8), M(3,8)  M and S/U(1) 1,2and and Q(6,8)
: 3. Power Range, Neutron Flux, High Positive Rate                  R(6)                  1,2
: 4. Power Range, Neutron Flux, High Negative Rate  N.A.            R(6)                  1,2
: 5. Intermediate Range, Neutron Flux                              R(6,8)        S/U(1)    1,2, and
: 6. Source Range, Neutron Flux                                    R(6,14)      M(14) Gild  2(7), 3(7), 4 and 5 S/U(1)
: 7. Overtemperature b,T                                            R(9)          M      1,2
: 8. Overpower hT                                                    R(9)                  1,2
: 9. Pressurizer Pressure Low                                                              1,2
: 10. Pressurizer Pressure High                                                            1,2
: 11. Pressurizer Water Level High                                                  M      1,2
: 12. Loss of Flow-Single Loop                                        R(8)
 
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3    INSTRUMENTATION TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION MINIMUM TOTAL NO.        CHANNELS          CHANNELS      APPLICABLE FUNCTIONALUNIT                OF CHANNELS      TO TRIP            OPERABLE        MODES        ACTION
: 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
: a. Steam Generator Water  3/Stm. Gen.      2/Stm. Gen.        2/Stm. Gen.      1,2, 3 Level  Low-Low                          any 2 Stm. Gen.                            14'.
Reactor Coolant Pump    4-1/Bus                                              1,2, 3 Bus Undervoltage                                                                      19'.
: 8. LOSS OF'POWER 4 kV Bus                3/Bus                                2/Bus          1,2,3,4 Loss of Voltage 14',2,3,4
: b. 4 kV Bus                3/Bus            2/Bus              2/Bus                    14 Degraded Voltage        P21A - Train 8;  (T21A - Tnin 8;    (TRIA-Tnin B; T21D - Tnin A)    TZID-Train A)      T21D-Tnin A)
: 9. MANUAL
: a. Safety Injection (ECCS) 2/train          1/train            2/train        1,2,3,4  18 Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase  "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
: b. Containment Spray      1/train          1/train            1/train        1,2,3,4  18 Containment Isolation-Phase  "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
: c. Containment Isolation-  1/train          1/train            1/train        1,2,3,4  18 Phase  "A" Containment Purge and Exhaust Isolation
: d. Steam Line Isolation    2/steam line      2/steam line      2/operating      1,2,3  20 (1 per train)    (1 per train)      steam line (1 per train)
COOK NUCLEAR PLANT-UNIT2                                  Page 3/4 3-20              AMENDMENTVV; 4%, 437
 
3/4        LIMlTINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3      INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCERE UIREMENTS TRIP ACTUATING    MODES IN CHANNEL              DEVICE      WHICH CHANNEL    CHANNEL      FUNCTIONAL          OPERATIONAL SURVEILLANCE FUNCFIONAL UNIT             CHECK  CALIBRATION          TEST  ~                      RE(EUIRED
: l. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
: a. Manual Initiation                                        Sec Functional Unit 9
: b. Automatic Actuation        N.A.                        M(2)                N.A.      I, 2, 3, 4 Logic
: c. Containment Pressure                                  M(3)                N.A.      I, 2, 3 High
: d. Pressurizer Pressure-                                                        N.A.      I, 2, 3 Low
: e. Differential Pressure                                                        N.A.      I, 2, 3 Between Steam    Lines High
: f. Steam Linc Pressure-                                                        N.A.      I, 2, 3 Low
: 2. CONTAINMENTSPRAY
: a. Manual Initiation                                  See Functional Unit 9
: b. Automatic Actuation                    N.A.            M(2)                N.A.      I, 2, 3, 4 Logic
: c. Containment Pressurc-                                  M(3)                N.A.      I, 2, 3 High-High
: 3. CONTAINMENT ISOLATION
: a. Phase    A Isolation I) Manual                                          Sec Functional Unit 9
: 2)    From Safety          N.A.      N.A.            M(2)                N.A.      I, 2, 3, 4 Injection Automatic Actuation Logic
: b. Phase    B Isolation I) Manual                                          See Functional Unit 9
: 2)    Automatic Actuation  N.A.      N.A.            M(2)                N.A.      I, 2, 3, 4 Logic
: 3)    Containment                                      M(3)                N.A.      I, 2, 3 Pressure- High-High COOK NUCLEAR PLANT-UNlT2                          Page 3/4 3-30                    AMENDMENT84,  9, 43V, 488
 
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3/4        LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3      INSTRUMENTATION TABLE4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCERE UIREMENTS TRIP ACTUATING  MODES IN CHANNEL              DEVICE      WHICH CHANNEL        FUNCfIONAL          OPERATIONAL SURVEILLANCE CHANNEL FUNCTIONALUNIT              CHECK    CALIBRATION          TEST                        RHtHUIRED
: c. Purge and Exhaust Isolation I) Manual                                          See Functional Unit 9
: 2)  Containment                                        e                  N.A.      I, 2, 3, 4 Radioactivity High
: 4. STEAM LINE ISOLATION
: a. Manual                                              See Functional Unit 9
: b. Automatic Actuation        N.A.      N.A.              M(2)                N.A.      I, 2, 3 Logic
: c. Containment Pressure                                  M(3)                N.A.      1,2,3 High-High
: d. Steam  How in Two Steam                                M                  N.A.      1,2,3 Lines High Coincident with T~ Low-Low
: c. Steam Line  Pressure-                                                      N.A.      1,2,3 Low
: 5. TURBINE TRIP AND FEEDWATER ISOLATION
: a. Steam Generator Water                                        M                  N.A.      1,2,3 Lcvcl  - High-High
: 6. MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
: a. Steam Generator Water                                                        N.A.      1,2,3 Level  Low-Low
: b. 4 kV Bus Loss of Voltage    S          R                M                  N.A.      1,2,3
: c. Safety Injection            N.A.      N.A.              M(2)                N.A.      I, 2, 3
: d. Loss  of Main Feed Pumps  N.A.      N.A.              R                  N.A.        1,2 COOK NUCLEAR PLANT-UNIT2                          Page 3/4 3-31              AMENDMENT%,%, 43k, 434,      4&V,
 
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3/4    LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,3  INFIRUMENTATION INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATIONMONITORING INSTRUMENTATION LIMITINGCONDITION FOR OPERATION 3.3.3.1      The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
APPLICABILITY:          As shown in Table 3.3-6.
ACTION:
With  a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable.
: b.        With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
: c.        The provisions  of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCERE UIREMENTS 4.3.3.1      Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONALTEST operations during the modes and at the frequencies shown in Table 4.3-3.
COOK NUCLEAR PLANT-UNIT2                          Page 3/4 3-34
 
TABLE4.3-6A APPENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCERE UIREMENTS 0
0                                                                                            CHANNEL                CHANNEL INSTRUMENT                                                        LOCATION                CHECK              CALIBRATION R
C O  1.        Steam Generators  1 and 4 Level                    LSI Cabinet 1  and LSI Cabinet 4
: 2.        Steam Generators 2 and 3 Level                      LSI Cabinet 2 and LSI Cabinet 4 R
I 3.        Steam Generators  1 and 4 Pressure                  LSI Cabinet 4 and LSI Cabinet 5 R
: 4.        Steam Generators 2 and 3 Pressure                  LSI Cabinet 4 and LSI Cabinet 6
: 5.        Reactor Coolant Loop 4 Temperature (Cold)          LSI Cabinet 4 and LSI Cabinet 5
: 6.        Reactor Coolant Loop 4 Temperature (Hot)            LSI Cabinet 4 and LSI                                  ,R Cabinet 5 tA 4J 7.        Reactor Coolant Loop 2 Temperature (Cold)          LSI Cabinet 4 and LSI Cabinet 6 C4 Reactor Coolant Loop 2 Temperature (Hot)            LSI Cabinet 4 and LSI Cabinet 6
: 9.        Pressurizer Level                                , LSI Cabinet 3                    M
: 10.      Reactor Coolant System Pressure                    LSI Cabinet 3
: 11.      Charging Cross-Flow Between Units                  Corridor Elev.
587'SI
: 12.      Source Range Neutron Detector (N-23)                   Cabinet 4
    *Charging Cross-Flow between Units is an instrument common to both Unit I and 2. This surveillance will only be  conducted on an interval consistent with Unit I refueling.
 
TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATIONSURVEILLANCERE UIREMENTS INSTRUMENT                                                                                  CHANNEL        CHANNEL CHECK        CALIBRATION
: 1.      Containment Pressure                                                                    M            R
: 2.      Reactor Coolant Outlet Temperature - Tnor (Wide Range)                                  M            R
: 3.      Reactor Coolant Inlet Temperature - Tco~ (Wide Range)                                    M            R
: 4.      Reactor Coolant Pressure - Wide Range                                                    M            R
: 5.      Pressurizer Water Level                                                                  M            R
: 6.      Steam Line Pressure                                                                      M            R
: 7.      Steam Generator Water Level - Narrow Range                                              M            R
: 8.      RWST Water Level                                                                        M            R
: 9.      Boric Acid Tank Solution Level                                                          M            R
: 10. Auxiliary Feedwater Flow Rate                                                            M            R
: 11. Reactor Coolant System Subcooling Margin Monitor                                        M            R
: 12. PORV Position Indicator - Limit Switches                                                M            R
: 13. PORV Block Valve Position Indicator - Limit Switches                                    M            R
: 14. Safety Valve Position Indicator - Acoustic Monitor                                      M            R
: 15. Incore Thermocouples (Core Exit Thermocouples)                                          M            Rtu
: 16. Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)              Mu~          RP)
: 17. Containment Sump Level                                                                  M            R
: 18. Containment Water Level                                                                  M            R tnPartial range channel calibration for sensor to be performed below P-12 in MODE 3.
"Kithone train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.
+Completion of channel calibration for sensors to be performed below P-12 in MODE 3.
 
TABLE 4.4-2
 
0 0                                                              STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION                                  2ND SAMPLE INSPECTION                        3RD SAMPLE INSPECTION Sample Size      Result        Action Required                Result              Action Required          Result        Action Required A minimum of S        C-1                  None                      N/A                      N/A                N/A                  N/A Tubes per S.G.
C-2    Plug defective tubes and                C-1                      None                N/A                  N/A inspect additional 2S tubes in this S.G.
C-2        Plug defective tubes and        C-1    None inspect additional 4S tubes in this S.G.
C-2    Plug defective tubes C-3    Perform action for C-3 result of first sample C-3        Perform action for C-3 result of first sample          N/A                  N/A C-3    Inspect all tubes in this S.G.,  All other plug defective tubes and        S.G.s are C  1    None                            N/A                  N/A inspect 2S tubes in each other S.G.
Prompt notification to NRC pursuant to specification 6.9.1 Some S.G.s        Perform action for C-2 C-2 but no        result of second sample          N/A                  N/A additional S.G.
are C-3.
Additional        Inspect all tubes in each      '/A                    N/A S.G. is C-3      S.G. and plug defective tubes. Prompt notification to NRC pursuant to specification 6.9.1.
S=3(N+n)%    Where N is the number  of steam  generators in the unit, and n is the number    of steam generators inspected during an inspection.
 
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4    REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITINGCONDITION FOR OPERATION 3.4.6.1          The following Reactor Coolant System leakage detection systems shall be OPERABLE:
a1      One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or ERS-2401),
The containment sump level and flow monitoring system, and Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).
APPLICABILITY:            MODES    1, 2, 3 and 4 ACTION:
With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE RE UIREMENTS 4.4.6.1          The leakage detection systems shall be demonstrated OPERABLE by:
Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONALTEST at the frequencies specified in Table 4.3-3.
Containment    sump  level and flow monitoring system-perfo'rmance      of CHANNEL CALIBRATIONat least once per      18 months.
C.      Containment    humidity monitor (if being    used)  - performance    of CHANNEL CALIBRATIONat least once per 18 months.
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4    REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION Continued With PORVs and block valves not in the same line inoperable due to causes other than excessive seat leakage, within 1 hour restore the valves to OPERABLE status or close and de-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.
: h.      The provisions  of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.1 F 1      In addition to the requirements      of Specification 4.0.5,    each PORV shall be demonstrated OPERABLE:
: a.      At  least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
: b.      At least once per  18 months  by operating the PORV through one complete cycle of full travel during MODES 3 or 4, and
: c.      At least  once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and
: d.      At least once per    18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation.
4.4.1 1.2      Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.11.
4.4.1 1.3      Deleted.
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4    REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM
                                        "'EACTOR VESSEL HEAD VENTS SURVEILLANCE RE UIREMENTS 4.4.12.1      Both Reactor Vessel head vent paths shall be demonstrated      OPERABLE at least once per 18 months by:
Verifying the common manual isolation valve in the Reactor vessel head vent is sealed in the open position.
Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
Verifying flow through both of the Reactor Vessel head vent paths during venting operation, while in Modes 5 or 6.
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4    REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS SURVEILLANCERE UIREMENTS 4.4.12.2      Both Pressurizer steam space vent paths shall be demonstrated OPERABLE at least once per 18 months by:
: 1.      Verifying the common manual isolation valve in the Pressurizer steam space vent is sealed in the open position.
: 2.      Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
: 3.      Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.
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3/4    LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,5  EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCERE UIREMENTS 4.5.2  Each ECCS subsystem shall be demonstrated OPERABLE:
ao      At least          once per 12 hours by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number                        Valve Function                              Valve Position
: a. IM0-390                              RWST to RHR                            a. Open
: b. IMO-315                        b. Low head SI to Hot Leg                b. Closed
: c. IM0-325                        c. Low head SI to Hot Leg                c. Closed
: d. IM0-262'.                     d. Mini flow line                        d. Open IM0-263                        e. Mini flow line                        e. Open
: f. ~                               f. SI Suction                            f. Open ICM-306'.h.
IM0-261'.
ICM-305'l.
ICM-305'l.
ICM-306'.
: g. Sump Line                              g. Closed Sump Line                              h. Closed
RWSTtoRHRb.LowheadSItoHotLegc.LowheadSItoHotLegd.Miniflowlinee.Miniflowlinef.SISuctiong.SumpLineh.SumpLinea.Openb.Closedc.Closedd.Opene.Openf.Openg.Closedh.Closedb.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) intheflowpaththatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
: b.     At least once per          31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.Byavisualinspection whichverifiesthatnoloosedebris(rags,trash,clothing, etc.)ispresentinthecontainment whichcouldbetransported tothecontainment sumpandcauserestriction ofthepumpsuctionsduringLOCAconditions.
: c.     By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
Thisvisualinspection shallbeperformed:
: 1.                 For all accessible  areas  of the containment prior to establishing    CONTAINMENT INTEGRITY, and
1.Forallaccessible areasofthecontainment priortoestablishing CONTAINMENT INTEGRITY, and2.Oftheareasaffectedwithincontainment atthecompletion ofeachcontainment entrywhenCONTAINMENT INTEGRITY isestablished.
: 2.                 Of the areas affected within containment at the completion    of  each containment entry when CONTAINMENTINTEGRITY is established.
Thesevalvesmustchangepositionduringtheswitchover frominjection torecirculation fiowfollowing LOCA.COOKNUCLEARPLANT-UNIT 2Page3/454~mnmmvs,m  
These valves must change position during the switchover from injection to recirculation fiow following LOCA.
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COOK NUCLEAR PLANT-UNIT2                                      Page 3/4 54                            ~mnmm vs, m
3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.5EMERGENCY CORECOOLINGSYSTEMS(ECCS)SURVEILLANCE REUIREMENTS 4.5.3.1,TheECCSsubsystem shallbedemonstrated OPERABLEpertheapplicable Surveillance
 
!Requirements of4.5.2.4.5.3.2Allchargingpumpsandsafetyinjection pumps,excepttheaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable, byverifying thatthemotorcircuitbreakershavebeenremovedfromtheirelectrical powersupplycircuits, atleastonceper12hourswheneverthetemperature ofoneormoreoftheRCScoldlegsislessthanorequalto15ZFasdetermined atleastonceperhourwhenanyRCScoldlegtemperature isbetween15ZFand200'F.COOKNUCLEARPLANT-UNIT 2Page3/454
  't A
.wa 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSSURVEILLANCE REUIREMENTS Continued Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaContainment Pressure-High-High testsignal.Atleastonceper5yearsbyverifying awaterflowrateofatleast20gpm(greaterthanorequalto20gpm)butnottoexceed50gpm(lessthanorequalto50gpm)fromthesprayadditivetanktestlinetoeachcontainment spraysystemwiththespraypumpoperating onrecirculation withapumpdischarge pressuregreaterthanorequalto255psig.COOKNUCLEARPLANT-UNIT 2Page3/46-12 p~a(~sII*V~~fC 3/4LIMrIINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSSURVEILLANCE REUIREMENTS Continued 4.6.3.1.2 Eachcontainment isolation valvespecified shallhcdemonstrated OPERABLEduringtheCOLDSHUTDOWNorREFUELING MODEatleastonceper18monthsby:Verifying thatonaPhaseAcontainment isolation testsignal,eachPhaseAisolation valveactuatestoitsisolation position.
U
Verifying thatonaPhaseBcontainment isolation testsignal,eachPhaseBisolation valveactuatestoitsisolation position.
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Verifying thatonaContainment PurgeandExhaustisolation signal,eachPurgeandExhaustvalveactuatestoitsisolation position.
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4.6.3.1.3 Theisolation timeofeachpoweroperatedorautomatic containment isolation valveshallbedetermined tobewithinitslimitwhentestedpursuanttoSpecification 4.0.5.COOKNUCLEARPLANT-UNIT 2Page3/46-14AMENDMENT PP,age,Sgg,Sdg e~4gIfII'veg~CjJf~gIt'IIf~~0'lli'JfII,Ifll1J 3/4LIMH'INGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSDIVIDERBARRIERSEALLIMITINGCONDITION FOROPERATION 3.6.5.9ThedividerbarriersealshallbeOPERABLE.
 
APPLICABILITY:
3/4    LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.5  EMERGENCY CORE COOLING SYSTEMS (ECCS)
MODES1,2,3and4.ACTION:Withthedividerbarriersealinoperable, restorethesealtoOPERABLEstatuspriortoincreasing theReactorCoolantSystemtemperature above200'F.SURVEILLANCE REUIREMENTS 4.6.5.9Thedividerbarriersealshallbedetermined OPERABLEatleastonceper18monthsduringshutdownby:Removingtwodividerbarriersealtestcouponsandverifying thatthephysicalproperties ofthetestcouponsarewithintheacceptable rangeofvaluesshowninTable3.6-2.Visuallyinspecting atleast95percentoftheseal'sentirelengthand:Verifying thatthesealandsealmountingboltsareproperlyinstalled, andVerifying thatthesealmaterialshowsnovisualevidenceofdeterioration duetoholes,ruptures, chemicalattack,abrasion, radiation damage,orchangesinphysicalappearances.
SURVEILLANCERE UIREMENTS 4.5.3.1,     The ECCS subsystem      shall be demonstrated  OPERABLE per the applicable Surveillance Requirements of 4.5.2.                                                                         !
COOKNUCLEARPLANT-UNIT 2Page3/46-47AMENDMENT V8,4R,459 lltil>t~Hyi'~I,gp)I.AlIs~r1"i<<e' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSi3/4.7.3COMPONENT COOLINGWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.3.1alAtleasttwoindependent component coolingwaterloopsshallbeOPERABLE.
4.5.3.2      All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours whenever the temperature of one or more of the RCS cold legs is less than or equal to 15ZF as determined at least once per hour when any RCS cold leg temperature is between 15ZF and 200'F.
Atleastonecomponent coolingwaterflowpathinsupportofUnit1shutdownfunctions shallbeavailable.
COOK NUCLEAR PLANT-UNIT2                      Page 3/4 54
APPLICABILITY:
 
ACTION:Specification 3.7.3.1.a.
.w a 3/4  LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS SURVEILLANCERE UIREMENTS Continued At least once per  18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure-High-High test signal.
-MODES1,2,3,4.Specification 3.7.3.1.b.
At least once per 5 years by verifying a water flow rate of at least 20 gpm (greater thanor equal to 20 gpm) but not to exceed 50 gpm (less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255psig.
-AtalltimeswhenUnit1isinMODES1,2,3,or4.WhenSpecification 3.7.3.1.a isapplicable:
COOK NUCLEAR PLANT-UNIT2                  Page 3/4 6-12
Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.3.1.b isapplicable:
 
WithnoflowpathtoUnit1available, returnatleastoneflowpathtoavailable statuswithin7days,orprovideIequivalent shutdowncapability inUnit1andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.
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SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:
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Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
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b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.Ic.Byverifying pumpperformance pursuanttoSpecification 4.0.5.d.Atleastonceper18monthsduringshutdown, verifythattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.
I
COOKNUCLEARPLANT-UNIT 2Page3/47-12AMENDMENT
* f  C
%,44G,43k,458  
 
~~'~,4'jt(~'g 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.4ESSENTIAL SERVICEWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.4.1a.Atleasttwoindependent essential servicewaterloopsshallbeOPERABLE.
3/4      LIMrIINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6    CONTAINMENTSYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3.1.2       Each containment isolation valve specified shall hc demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
b.Atleastoneessential servicewaterflowpathassociated withsupportofUnit1shutdownfunctions shallbeavailable.
Verifying that on    a Phase A containment isolation test signal, each  Phase  A isolation valve actuates to its isolation position.
APPLICABILITY:
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
Specification 3.7.4.1.a.
Verifying that on      a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.
-MODES1,2,3,and4.Specification 3.7.4.1.b.
4.6.3.1.3       The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
-AtalltimeswhenUnit1isinMODES1,2,3,or4.ACTION:WhenSpecification 3.7.4.1.a isapplicable:
COOK NUCLEAR PLANT-UNIT2                            Page 3/4 6-14                AMENDMENTPP, age, Sgg, Sdg
Withonlyoneessential servicewaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.4.1.b isapplicable:
 
Withnoessential servicewaterflowpathavailable insupportofUnit1shutdownfunctions, returnatleastonefiowpathtoavailable statuswithin7daysorprovideequivalent shutdowncapability inUnit1andreturntheequipment toservicewithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.
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SURVEILLANCE REUIREMENTS 4.7.4.1Atleasttwoessential servicewaterloopsshallbedemonstrated OPERABLE:
4 If                                        I' g              I                                    v t
Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.
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Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.COOKNUCLEARPLANT-UNIT 2Page3/47-13AMENDMENT
g  I If ~ ~ 0'll i' Jf II, I If ll 1 J
%,446,48k,458,459  
 
~tHC/nH 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSSURVEILLANCE REUIREMENTS Continued e.Atleastonceper18monthsby:1.Verifying thatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan6inchesWaterGaugewhileoperating theventilation systemataflowrateof6000cfmplusorminus10%.2.a.Verifying thatonaSafetyInjection SignalfromUnit1,thesystemautomatically operatesinthepressurization/cleanup mode.b.Verifying thatonaSafetyInjection SignalfromUnit2,thesystemautomatically operatesinthepressurization/cleanup mode.3.Verifying thatthesystemmaintains thecontrolroomatapositivepressureofgreaterthanorequalto1/16inchW.G.relativetotheoutsideatmosphere atasystemflowrateof6000cfmplusorminus10%.Aftereachcompleteorpartialreplacement ofaHEPAfilterbankbyverifying thattheHEPAfilterbanksremovegreaterthanorequalto99%oftheDOPwhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.iAftereachcompleteorpartialreplacement ofacharcoaladsorberbankbyverifying thatthecharcoaladsorbers removegreaterthanorequalto99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.COOKNUCLEARPLANT-UNIT 2Page3/47-16aAMENDMENT W,m,m,am os~dk'l>>g46~0I'eri" 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.7SNUBBERSLIMITINGCONDITION FOROPERATION 3.7.7.1Allsafety-related snubbersshallbeOPERABLE.
3/4      LIMH'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6    CONTAINMENTSYSTEMS DIVIDER BARRIER SEAL LIMITINGCONDITION FOR OPERATION 3.6.5.9          The divider barrier seal shall be OPERABLE.
APPLICABILITY:
APPLICABILITY:             MODES      1, 2, 3 and 4.
MODES1,2,3and4.(MODES5and6forsnubberslocatedonsystemsrequiredOPERABLEinthoseMODES).ACTION:Withoneormoresnubbersinoperable, within72hoursreplaceorrestoretheinoperable snubber(s) toOPERABLEstatusandperformanengineering evaluation perSpecification 4.7.7.1.c onthesupported component ordeclarethesupported systeminoperable andfollowtheappropriate ACTIONstatement forthatsystem.SURVEILLANCE REUIREMENTS 4.7.7.1Eachsnubbershallbedemonstrated OPERABLEbyperformance ofthefollowing augmented inservice inspection programandtherequirements ofSpecification 4.0.5.VisualInsctionSnubbersarecategorized asinaccessible oraccessible duringreactoroperation.
ACTION:
Eachofthesecategories (inaccessible andaccessible) maybeinspected independently according tothescheduledetermined byTable3.7-9.Thevisualinspection intervalforeachtypeofsnubbershallbedetermined baseduponthecriteriaprovidedinTable3.7-9andthefirstinspection intervaldetermined usingthiscriteriashallbebaseduponthepreviousinspection intervalasestablished bytherequirements ineffectbeforeAmendment No.156.VisualInsctionAccetanceCriteriaVisualinspections shallverify(1)thattherearenovisibleindications ofdamageorimpairedOPERABILITY, (2)attachments tothefoundation orsupporting structure aresecure,and(3)inthoselocations wheresnubbermovementcanbemanuallyinducedwithoutdisconnecting thesnubber,thatthesnubberhasfreedomofmovementandisnotfrozenup.Snubberswhichappearinoperable asaresultofvisualinspections shallbeclassified asunacceptable andmaybereclassified asacceptable forthepurposeofestablishing thenextvisualinspection
With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.
: interval, providing that(1)thecauseoftherejection isclearlyestablished andremediedforthatCOOKNUCLEARPLANT-UNIT 2Page3/47-20AMENDMENT ue,m,1,m rrIAh,l,a 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSELECTRICAL POWERSYSTEMSSHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.1.2Asaminimum,thefollowing A.C.electrical powersourcesshallbeOPERABLE:
SURVEILLANCE RE UIREMENTS 4.6.5.9          The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:
Onecircuitbetweentheoffsitetransmission networkandtheonsiteClass1Edistribution system,andOnedieselgenerator with:1.Adayfueltankcontaining aminimumof70gallonsoffuel.2.Afuelstoragesystemcontaining aminimumindicated volumeof46,000gallonsoffuel,andAPPLICABILITY:
Removing two divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.
3.Afueltransferpump.MODES5and6.ACI'ION:WilllessthantheaboveminimumrequiredA.C.electrical powersourcesOPERABLE, suspendalloperations involving COREALTERATIONS orpositivereactivity changes*untiltheminimumrequiredA.C.
Visually inspecting at least 95 percent of the seal's entire length and:
electrical powersourcesarerestoredtoOPERABLEstatus.SURVEILLANCE REUIREMENTS 4.8.1.2TheaboverequiredA.C.electrical powersourcesshallbedemonstrated OPERABLEbytheperformance ofeachoftheSurveillance Requirements of4.8.1.1.1 and4.8.1~1.2exceptfor!requirement 4.8.1~1.2.a.5.Forpurposeofthisspecification, additionof'waterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.
Verifying that the seal and seal mounting bolts are properly installed, and Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.
COOKNUCLEARPLANT-UNIT 2Page3/48-9AMENDMENT ARAN,444459 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSSURVEILLANCE REUIREMENTS Continued Atleastonceper92daysbyverifying that:Thevoltageofeachconnected cellisgreaterthanorequalto2.13voltsunderfloatcharge.Thespecificgravity,corrected to77'F,andfullelectrolyte level(fluidatthebottomofthemaximumlevelindication mark),ofeachconnected cellisgreaterthanorequalto1.200andhasnotdecreased morethan0.03fromthevalueobservedduringtheprevioustest,andTheelectrolyte levelofeachconnected cellisbetweenthetopoftheminimumlevelindication markandthebottomofthemaximumlevelindication mark.C.Atleastonceper18monthsbyverifying that:1.Thecells,cellplatesandbatteryracksshownovisualindication ofphysicaldamageorabnormaldeterioration, Thecell-to-cell andterminalconnections areclean,tight,freeofcorrosion andcoatedwithantieorrosion
COOK NUCLEAR PLANT-UNIT2                              Page 3/4 6-47                        AMENDMENTV8, 4R, 459
: material, 3.Thebatterychargerwillsupplyatleast140amperesatgreaterthanorequalto250voltsforatleast4hours.Atleastonceper18months,performabatteryservicetestduringshutdown(MODES5or6),byverifying thatthebatterycapacityisadequatetosupplyandmaintaininOPERABLEstatustheactualorsimulated emergency loadsforthedesigndutycyclewhichisbasedonthecomposite loadprofile.Thecomposite loadprofileenvelopes boththeLOCA/LOOP andStationBlackoutprofilesandprovidesthebasisforthetimeslistedinTable4.8-2.Thebatterychargerwillbedisconnected throughout thetest.Thebatteryterminalvoltageshallbemaintained greaterthanorequalto210voltsthroughout thistest.e.Atleastonceper60months,conductaperformance testofbatterycapacityduringshutdown(MODES5or6),byverifying thatthebatterycapacityisatleast80%ofthemanufacturer's rating.Whenthistestisperformed inplaceofabatteryservicetest,amodifiedperformance testshallbeconducted.
 
Annualperformance testsofbatterycapacityshallbegiventoanybatterythatshowssignsofdegradation orhasreached85%oftheservicelifeexpectedfortheapplication.
ll ti l> t ~ Hyi ' ~ I, gp) I. Al  s ~ r 1" i<<e' I
Degradation isindicated whenthebatterycapacitydropsmorethan10%fromitscapacityonthepreviousperformance test,orisbelow90%ofthemanufacturer's rating.Ifthebatteryhasreached85%ofservicelife,deliversacapacityof100%orgreaterofthemanufacturer's ratedcapacity, andhasshownnosignsofdegradation, performance testingattwoyearintervals isacceptable untilthebatteryshowssignsofdegradation.
 
COOKNUCLEARPLANT-UNIT 2Page3/48-13AMENDMENT 448,489,466,46 II~~
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7    PLANT SYSTEMS                          i 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.3.1 al        At least two independent component cooling water loops shall    be OPERABLE.
3/4.0LIMI'rING CONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSD.C.DISTRIBUTION
At least  one component cooling water flow path in support    of Unit 1 shutdown functions shall be available.
-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.2.4Asaminimum,thefollowing D.C.electrical equipment andbusshallbeenergized andOPERABLE:
APPLICABILITY:               Specification 3.7.3.1.a. - MODES 1, 2, 3, 4.
1-250-voltD.C.bus,and1-250-voltbatterybankandchargerassociated withtheaboveD.C.bus.APPLICABILITY:
Specification 3.7.3.1.b. - At all times when Unit  1 is in MODES 1, 2, 3, or 4.
MODES5and6.ACTION:Withlessthantheabovecomplement ofD.C.equipment andbusOPERABLE, establish CONTAINMENT INTEGRITY within8hours.SURVEILLANCE REUIREMENTS 4.8.2.4.1 Theaboverequired250-voltD.C.busshallbedetermined OPERABLEandenergized atleastonceper7daysbyverifying correctbreakeralignment andindicated poweravailability.
ACTION:
4.8.2.4.2 Theaboverequired250-voltbatterybankandchargershallbedemonstrated OPERABLEperSurveillance Requirement 4.8.2.3.2.
When Specification 3.7.3.1.a is applicable:
ICOOKNUCLEARPLANT-UNIT 2Page3/48-15AMENDMENTS, ae,m Iv,~t 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.9REFUELING OPERATIONS STORAGEPOOLVENTILATION SYSTEM"LIMITINGCONDITION FOROPERATION 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
APPLICABILITY:
When Specification 3.7.3.1.b is applicable:
Wheneverirradiated fuelisinthestoragepool.ACTION:a.Withnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool+
With no flowpath to Unit      1 available, return at least one flowpath to available status within 7 days, or provide      I equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours and HOT SHUTDOWN within the following 24 hours.
untilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus'.Theprovisions ofSpeciflcations3.0.3 and3.0.4arenotapplicable.
The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE REUIREMENTS 4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:
SURVEILLANCE RE UIREMENTS 4.7.3.1            At least two component cooling water loops shall be demonstrated OPERABLE:
a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.AtleastonceperISmonthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following
At  least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
: painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove299%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfmk10%.'Thecranebayroii-updoorandthesouthdooroftheauxiliary buildingcranebaymaybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool."SharedsystemwithD.C.Cook-Unit1.+Thisdocsnotincludethemainloadblock.Forpurposesofthisspecification, adeenergized mainloadblockneednotbeconsidered aload.COOKNUCLEARPLANT-UNIT 2Page3/49-12AMENDMENT 444 5.0DESIGNFEATURES5.6FUELSTORAGE Continued CRITICALITY-SPENTFUELContinued Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations:
: b.       At  least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test I
IForReion2Stora eMinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,2608
signal.
+149E3ForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E'98.4EiWhereE=InitialPeakEnrichment 5.6.1.2MaximumNominalFuelAssemblyEnrichment Wt.%U-235FuelstoredinthespentfuelstorageracksshaHhaveanominalfuelassemblyenrichment asfollows:Description 1)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.954.954.95COOKNUCLEARPLANT-UNIT 2Page54AMENDMENT 4k,49k,447,483,498 5.0DESIGNFEATURESFigure5.6-3intentionally deleted.COOKNUCLEARPLANT-UNIT 2Page5-8  
: c.       By verifying pump performance pursuant to Specification 4.0.5.
~'I~Q~I0IIeaIIlkfiiP'I'I]lal
: d.       At least once per 18 months during shutdown, verify that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.
<Ii6.0ADMINISTRATIVE CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilistaffshtyallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustbequalified asspecified inSection6.2.2.g.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTIONThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.
COOK NUCLEAR PLANT-UNIT2                              Page 3/4 7-12                  AMENDMENT%,           44G, 43k, 458
Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Technical Support,Licensing, Maintenance andRadiation Protection.
 
ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.
              ~ ~
Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexcccdtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.
4'   j t( ~,'g
Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.
          ~
COOKNUCLEARPLANT-UNIT 2Page6-4AMENDMENT 34,447,438,4',4VS,493 ATTACHMENT 4TOAEP:NRC:0433Q 4EVALUATION OFSIGNIFICANT HAZARDSCONSIDERATION Attachment 4toAEP:NRC:0433Q Page1Evaluation ofSinificantHazardsConsideration TheLicenseehasevaluated thisproposedamendment anddetermined thatitinvolvesnosignificant hazardsconsideration.
 
According to10CFR50.92(c),
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7    PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.4.1
aproposedamendment toanoperating licenseinvolvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:1.involveasignificant increaseintheprobability ofoccurrence orconsequences ofanaccidentpreviously evaluated; 2.createthepossibility ofanewordifferent kindofaccidentfromanypreviously analyzed; or3.involveasignificant reduction inamarginofsafety.TheLicenseeproposestomakeadministrative changestoseveraltechnical specifications (T/S)forDonaldC.CookNuclearPlantunit1andunit2.Theproposedchangesinclude:(1)revisingboronsamplingrequirements inmode6;(2)deletingareference toobsoleteequipment inafootnote; (3)deletingaredundant figure;(4)correcting areference toanotherrequirement; (5)deletingobsoletenotes;(6)addingtosurveillance requirements; (7)clarifying instrumentation configuration; and(8)correcting typographical errors.Thesechangesareproposedtoremoveobsoleteinformation, provideconsistency betweenunit1andunit2,provideconsistency withtheStandardTechnical Specifications, provideclarification, andcorrecttypographical errors.Thedetermination thatthecriteriasetforthin10CFR50.92aremetforthisamendment requestisindicated below.1.Doesthechangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?
: a.       At least two independent essential service water loops shall be OPERABLE.
Theproposedchangeforboronsamplingrequirements inmode6doesnotaffecttheprobability ofafuelhandlingaccident.
: b.       At least one essential service water flowpath    associated with support of Unit  1 shutdown functions shall be available.
Theunlikelyeventofafuelassemblybeingmisloaded isindependent ofthesamplingfrequency forfuelpoolboronconcentration.
APPLICABILITY:               Specification 3.7.4.1.a. - MODES 1, 2, 3, and 4.
Ithasnoimpactontheeventinitiator, whichisahumanerrorwhilepositioning afuelassembly.
Specification 3.7.4.1.b. - At all times when Unit 1 is in MODES 1, 2, 3, or 4.
Thechangehasnoimpactonthe*assumptions forafuelhandlingaccident.
ACTION:
Theboronconcentration requirement isnotchanged;thereissufficient boroninthefuelstoragepooltomaintaink,qqbelow0.95toprecludeaninadvertent criticality.
When Specification 3.7.4.1.a is applicable:
Therefore, theconsequences oftheaccidentwillbemitigated aspreviously evaluated.
With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours or be in at least HOT STANDBYwithin the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
The72-hourmaximumintervalbetweensamplesismaintained.
When Specification 3.7.4.1.b is applicable:
Operating experience hasshown72hourstobeadequate.
With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one fiow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours and HOT SHUTDOWN within the following 24 hours. The requirements of Specification 3.0.4 are not applicable.
Removingtheadditional limitation ofsamplingatleastthreetimesperweekwouldallowthesampletobecollected twoorthreetimesperweek,consistent withthemaximum72-hourinterval.
SURVEILLANCERE UIREMENTS 4.7.4.1            At least two essential service water loops shall be demonstrated OPERABLE:
Thisisacceptable becauseboronconcentration changesoccurslowlyduetothelarge 1
At least once per    31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
Attachment 4toAEP:NRC:0433Q Page2volumeofwaterinthesystemandrelatively smallvolumesofdilutionsources.Theconsequences arenotincreased becausetherearenochangestothespentfuel,shielding (water),orsystemsusedtomitigatetheconsequences ofanaccident.
At  least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.
Additionally, thereisnochangeinthetypesorsignificant increaseintheamountsofanyeffluents releasedoffsite.Deletingtheredundant figureforequivalent reactivity criteriaforregionsinthespentfuelstorageracksdoesnotimpactthestoragerequirements becausetheequations provideequivalent requirements.
COOK NUCLEAR PLANT-UNIT2                              Page 3/4 7-13              AMENDMENT%, 446, 48k, 458, 459
Theunlikelyeventofafuelassemblybeingmisloaded isindependent ofthecharacteristics ofthespentfuelinthepool.Ithasnoimpactontheeventinitiator, whichisahumanerrorwhilepositioning afuelassembly.
 
Thechangehasnoimpacttheassumptions forafuelhandlingaccidentbecausethefuelstoragerequirements arenotchanged.Theconsequences ofanaccidentarenotincreased becausethefuelstoragerequirements arenotchangedandnootherchangesaremadetosystemsthatmitigatetheconsequences ofanaccident.
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Theproposedchangestocorrectareference toanotherrequirement, deleteobsoletenotes,revisethenameofdrummingroomroll-updoor,andcorrecttypographical errorsareconsidered administrative.
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Thereference leadstoasectionthatnolongerexists;theproposedchangecorrectstheerror.Thenotespermitted exceptions torequirements, andtheyarenolongerrequired.
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Thenormalrequirements haveappliedsincetheprovisions expired.Deletingthemeliminates extraneous information.
 
Thereviseddescription ofthedoorreflectsthecurrentuseoftheinstalled door.Correcting thetypographical errorsimprovesreadability.
3/4  LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCERE UIREMENTS Continued
Thecorrections arenotintendedtochangethemeaning.Thesechangesdonotaffectaccidents described intheUFSAR.Addingnewsurveillance requirements totesttheunit2pumpperformance pursuanttoT/S4.0.5doesnotaffectaccidentinitiators orprecursors.
: e. At least once per  18 months  by:
ThechangereflectsASMEcoderequirements.
: 1.       Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
Including therequirements inthecorresponding sectionprovidesassurance thatthepumpswilloperateasassumedintheaccidentanalyses.
: 2.       a.       Verifying that on a Safety Injection Signal from Unit      1, the system automatically operates in the pressurization/cleanup mode.
Assuch,theprobability and'onsequences ofpreviously evaluated accidents isunchanged.
: b.       Verifying that on a Safety Injection Signal from Unit 2, the system automatically operates in the pressurization/cleanup mode.
Theproposedchangetothedescription ofinstrumentation configuration isconsidered administrative becausetheconfiguration hadbeenreviewedandapprovedbytheNRCStaff,asdocumented intheSafetyEvaluation Reportforamendment 39forDPR-58andamendment 22forDPR-74.Therearenochangestotheactualplantconfiguration.
: 3.       Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W. G. relative to the outside atmosphere at a system flow rate of 6000 cfm plus or minus 10%.
Thechangeisintendedtodescribetheinstalled equipment moreclearly.Thechangedoesnotaffecttheprobability andconsequences ofpreviously evaluated accidents becausetheequipment isinstalled andoperatedasdescribed inthecorrespondence relatedtothepreviousamendments.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
Basedonthisreview,itisconcluded thattheproposedchangesdonotinvolveasignificant increaseinthe L.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon i                  refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
Attachment 4toAEP:NRC:0433Q Page3probability ofoccurrence orconsequences ofanaccidentpreviously evaluated.
COOK NUCLEAR PLANT-UNIT2                  Page 3/4 7-16a                  AMENDMENTW, m,           m, am
2.Doesthechangecreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated' Theproposedchangesremoveobsoleteinformation, provideconsistency betweenunit1andunit2,provideconsistency withtheStandardTechnical Specifications, provideclarification, andcorrecttypographical errors.Thesechangesareconsidered administrative becausetheydonotaffectthedesignoroperation ofanysystem,structure, orcomponent intheplant~Theaccidentanalysisassumptions andresultsareunchanged.
 
Nonewfailuresorinteractions havebeencreated.Basedonthisreview,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.
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3.Doesthechangeinvolveasignificant reduction inamarginofsafety?Theproposedchangesareconsidered administrative innature.TheydonotaffectanysafetylimitsorT/Sparameter limits.Theproposedchangesdonotintroduce newequipment, equipment modifications, ornewordifferent modesofplantoperation.
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Thesechangesdonotaffecttheoperational characteristics ofanyequipment orsystems.Basedonthisreview,itisconcluded thatnoreduction inthemarginofsafetywilloccurasaresultofthechanges.'nsummary,basedupontheaboveevaluation, theLicenseehasconcluded thatthesechangesinvolvenosignificant hazards'onsideration.
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ATTACHMENT 5TOAEP:NRC:0433Q ENVIRONMENTAL ASSESSMENT  
 
3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7    PLANT SYSTEMS 3/4.7.7 SNUBBERS LIMITINGCONDITION FOR OPERATION 3.7.7.1          All safety-related snubbers shall be OPERABLE.
APPLICABILITY:             MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREMENTS 4.7.7.1          Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
Visual Ins    ction Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-9. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-9 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No.
156.
Visual Ins    ction Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified as acceptable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that COOK NUCLEAR PLANT-UNIT2                              Page 3/4 7-20                AMENDMENTue,           m, 1, m
 
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8    ELECTRICALPOWER SYSTEMS ELECTRICALPOWER SYSTEMS SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.1.2            As a minimum, the followingA.C. electrical power sources shall be OPERABLE:
One circuit between the offsite transmission network and the onsite Class 1E distribution system, and One diesel generator with:
: 1.       A day fuel tank containing  a minimum of 70 gallons of fuel.
: 2.       A fuel storage system containing  a minimum indicated volume  of 46,000 gallons of fuel, and
: 3.       A fuel transfer pump.
APPLICABILITY:              MODES 5 and 6.
ACI'ION:
Will less than the above minimum required A.C. electrical power        sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes* until the minimum requiredA.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCERE UIREMENTS 4.8.1.2            The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1 1.2 except for
                                                                                                    ~
requirement 4.8.1 1.2.a.5.
                                    ~
For purpose of this specification, addition of'water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.
COOK NUCLEAR PLANT-UNIT2                            Page 3/4 8-9                    AMENDMENTARAN, 444 459
 
3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS SURVEILLANCERE UIREMENTS Continued At least once per 92 days by verifying that:
The voltage  of each  connected cell is greater than or equal to 2.13 volts under float charge.
The specific gravity, corrected to 77'F, and full electrolyte level (fluid at the bottom of the maximum level indication mark), of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.
C. At least once per  18 months  by verifying that:
: 1.       The cells, cell plates and battery racks show no visual indication      of physical damage or abnormal deterioration, The cell-to-cell and terminal connections are clean, tight, free  of corrosion and coated with antieorrosion material,
: 3.       The battery charger will supply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours.
At least  once per 18 months, perform a battery service test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2. The battery charger will be disconnected throughout the test. The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this test.
: e. At  least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.
Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.
Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. If the battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.
COOK NUCLEAR PLANT-UNIT2                            Page 3/4 8-13        AMENDMENT448, 489, 466,         46
 
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3/4.0    LIMI'rINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8    ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.2.4          As a minimum, the following D.C. electrical equipment and bus shall be energized          and OPERABLE:
1 - 250-volt D.C. bus, and 1 - 250-volt battery bank and charger associated with the above D.C. bus.
APPLICABILITY:             MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours.
SURVEILLANCERE UIREMENTS 4.8.2.4.1       The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2       The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.                                                           I COOK NUCLEAR PLANT-UNIT2                                  Page 3/4 8-15            AMENDMENTS, ae,       m
 
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3/4      LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.9    REFUELING OPERATIONS STORAGE POOL VENTILATIONSYSTEM" LIMITINGCONDITION FOR OPERATION 3.9.12  The spent fuel storage pool exhaust ventilation system shall be OPERABLE.
APPLICABILITY:             Whenever irradiated fuel is in the storage pool.
ACTION:
: a.       With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storagepool+ until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE  status'.
The provisions of Speciflcations3.0.3 and 3.0.4 are not applicable.
SURVEILLANCERE UIREMENTS 4.9.12  The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:
: a.       At least once per  31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.
At least once per IS months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
: 1.       Deleted.
: 2.       Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfmk 10%.
'The crane bay roii-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.
"Shared system with D. C. Cook - Unit 1.
+This docs not include the main load block. For purposes of this specification, adeenergized main load block need not be considered a load.
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5.0    DESIGN FEATURES 5.6 FUELSTORAGE Continued CRITICALITY-SPENT FUEL Continued The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations:                                                                               I For Re ion2Stora      e Minimum Assembly Average Burnup in MWD/MTU=
                                  -22,670+ 22,220E-2,2608 +           149 E3 For Re ion 3 Stora    e Minimum Assembly Average Burnup in MWD/MTU=
                                  -26,745+   18,746 E - 1,631 E'     98.4 Ei Where E  = Initial Peak  Enrichment 5.6.1.2        Fuel stored in the spent fuel storage racks    shaH  have a nominal fuel assembly enrichment as follows:
Description                                        Maximum Nominal Fuel Assembly Enrichment Wt. % U-235
: 1)     Westinghouse             15 x 15  STD                            4.95 15 x 15  OFA
: 2)       Exxon/ANF               15x 15                                  4.95
: 3)       Westinghouse             17 x 17  STD                            4.95 17 x 17  OFA 17x17V5
: 4)       Exxon/AN F              17x  17                                4.95 COOK NUCLEARPLANT-UNIT2                            Page  54                AMENDMENT4k, 49k, 447, 483, 498
 
5.0  DESIGN FEATURES Figure 5.6-3 intentionally deleted.
COOK NUCLEAR PLANT-UNIT2            Page 5-8
 
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6.0    ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF          UALIFICATIONS 6.3.1  Each member of the facility staff sh all meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must be qualified as specified in Section 6.2.2.g.
6.4 TRAINING 6.4.1  A retraining and replacement training program for the facility staff shall be maintained under the direction  of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5              of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.
COMPOSITION 6.5.1.2          The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Technical Support, Licensing, Maintenance and Radiation Protection.
The PNSRC membership shall consist of at least one individual from each of the areas designated.
All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.
PNSRC members and alternates shall meet or excccd the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
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ATTACHMENT 4 TO AEP:NRC:0433Q 4
EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION to  AEP:NRC:0433Q                                 Page  1 Evaluation of Si nificant Hazards Consideration The Licensee has      evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
: 1. involve a significant increase            in the probability of occurrence or consequences          of an accident previously evaluated;
: 2. create      the possibility of a new or different kind of accident from any previously analyzed; or
: 3. involve      a significant reduction in    a margin of safety.
The Licensee      proposes to make administrative changes to several technical specifications (T/S) for Donald C. Cook Nuclear Plant unit 1 and unit 2. The proposed changes include: (1) revising boron sampling requirements in mode 6; (2) deleting a reference to obsolete equipment in a footnote; (3) deleting a redundant figure; (4) correcting a reference to another requirement; (5) deleting obsolete notes; (6) adding to surveillance requirements; (7) clarifying instrumentation configuration; and (8) correcting typographical errors.           These changes are proposed to remove obsolete information, provide consistency between unit 1 and unit 2, provide consistency with the Standard Technical Specifications, provide clarification, and correct typographical errors.
The determination that the criteria set forth in 10 CFR 50.92 are met for this amendment request is indicated below.
: 1. Does    the    change  involve  a  significant increase    in the probability        or  consequences    of  an  accident  previously evaluated?
The proposed      change for boron sampling requirements in mode 6 does not    affect the probability of a fuel handling accident.
The unlikely event of a fuel assembly being misloaded is independent of the sampling frequency for fuel pool boron concentration. It has no impact on the event initiator, which is a human error while positioning a fuel assembly.                 The change has no impact on the* assumptions for a fuel handling accident. The boron concentration requirement is not changed; there is sufficient boron in the fuel storage pool to maintain k,qq  below 0.95 to preclude an inadvertent criticality.
Therefore, the consequences of the accident will be mitigated as previously evaluated.       The 72-hour maximum interval between samples is maintained.           Operating experience has shown 72 hours to be adequate.         Removing the additional limitation of sampling at least three times per week would allow the sample to be collected two or three times per week, consistent with the maximum 72-hour interval.             This is acceptable because boron concentration changes occur slowly due to the large
 
1   to AEP:NRC:0433Q                                         Page 2 volume  of water in the system and relatively small volumes of dilution    sources. The consequences      are not increased because there are no changes to the spent fuel, shielding (water), or systems used to mitigate the consequences                  of an accident.
Additionally, there is no change in the types or significant increase in the amounts of any effluents released offsite.
Deleting the redundant figure for equivalent reactivity criteria for regions in the spent fuel storage racks does not impact the storage requirements because the equations provide equivalent requirements.             The unlikely event of a fuel assembly being misloaded is independent of the characteristics of the spent fuel in the pool. It has no impact on the event initiator, which is a human error while positioning a fuel assembly. The change has no impact the assumptions for a fuel handling accident because the fuel storage requirements are not changed.         The consequences        of an accident are not increased because the fuel storage requirements are not changed and no other changes are made to systems that mitigate the consequences of an accident.
The proposed      changes    to correct a reference to another requirement,     delete obsolete notes, revise the name of drumming room roll-up door, and correct typographical errors are considered administrative.               The reference      leads to a section that no longer exists; the proposed change corrects the error.     The notes permitted exceptions to requirements, and they are no longer required.           The normal requirements have applied since the provisions expired.                       Deleting them eliminates extraneous information. The revised description of the door reflects the current use of the installed door.
Correcting the typographical errors improves readability. The corrections are not intended to change the meaning.                     These changes do not affect accidents described in the UFSAR.
Adding new surveillance requirements to test the unit 2 pump performance pursuant to T/S 4.0.5 does not affect accident initiators or precursors.             The change reflects ASME code requirements.     Including the requirements in the corresponding section provides assurance that the pumps will operate as assumed in the accident          analyses.     As such,   the probability and 'onsequences         of    previously      evaluated     accidents   is unchanged.
The  proposed    change    to the description of instrumentation configuration       is    considered      administrative because        the configuration    had been reviewed and approved by the NRC Staff, as documented in the Safety Evaluation Report for amendment 39 for DPR-58 and amendment 22 for DPR-74. There are no changes to the actual plant configuration. The change is intended to describe the installed equipment more clearly.                   The change does not affect the probability and consequences of previously evaluated accidents because the equipment is installed and operated as described in the correspondence related to the previous amendments.
Based on this review, changes    do not involve it a is significant concluded  that the proposed increase    in the
 
L.
Attachment   4 to  AEP:NRC:0433Q                                     Page 3 probability of occurrence            or consequences    of  an  accident previously evaluated.
: 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated' The  proposed    changes remove obsolete information, provide consistency    between unit 1 and unit 2, provide consistency with the        Standard      Technical      Specifications,     provide clarification,     and  correct typographical errors.             These changes are considered administrative because they do not affect the design or operation of any system, structure, or component in the plant    ~ The accident analysis assumptions and results are unchanged.       No new failures or interactions have been created.       Based on this review, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
: 3. Does the change involve a      significant reduction in      a margin of safety?
The proposed changes are considered administrative in nature.
They do not affect any safety limits or T/S parameter limits.
The proposed changes do not introduce new equipment, equipment modifications, or new or different modes of plant operation.
These changes do not affect the operational characteristics of any equipment or systems.             Based on this review, concluded that no reduction in the margin of safety            will it  is occur as a result of the changes.
                                      'n summary,   based  upon  the above evaluation, the Licensee has concluded    that these    changes    involve no significant hazards
'onsideration.
 
ATTACHMENT 5 TO AEP:NRC:0433Q ENVIRONMENTAL ASSESSMENT
 
to  AEP:NRC:0433Q                                    Page  1 Environmental Assessment The  Licensee has evaluated      this license    amendment  request against the    criteria for identification of licensing              and  regulatory actions    requiring environmental        assessment    in accordance with 10 CFR 51.21.        The Licensee has determined that this license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) . This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria.
(i)    The      amendment      involves      no    significant      hazards consideration.
As demonstrated      in attachment    4,  this  proposed  amendment does not    involve any significant hazards consideration.
(ii)  There    is  no significant change .in the types or significant increase      in the amounts of any effluent that may be released    offsite.
As documented      in attachment 4, there will be no change in the types or significant increase in the amounts of any effluents released offsite.
(iii) There      is no significant increase in              individual    or cumulative occupational radiation exposure.
The  proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant.
Therefore, 'here will be no increase in individual or cumulative occupational radiation exposure resulting from this  change.


Attachment 5toAEP:NRC:0433Q Page1Environmental Assessment TheLicenseehasevaluated thislicenseamendment requestagainstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.TheLicenseehasdetermined thatthislicenseamendment requestmeetsthecriteriaforacategorical exclusion setforthin10CFR51.22(c)(9)
l i
.Thisdetermination isbasedonthefactthatthischangeisbeingproposedasanamendment toalicenseissuedpursuantto10CFR50thatchangesarequirement withrespecttoinstallation oruseofafacilitycomponent locatedwithintherestricted area,asdefinedin10CFR20,orthatchangesaninspection orasurveillance requirement, andtheamendment meetsthefollowing specificcriteria.
  *}}
(i)Theamendment involvesnosignificant hazardsconsideration.
Asdemonstrated inattachment 4,thisproposedamendment doesnotinvolveanysignificant hazardsconsideration.
(ii)Thereisnosignificant change.inthetypesorsignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite.Asdocumented inattachment 4,therewillbenochangeinthetypesorsignificant increaseintheamountsofanyeffluents releasedoffsite.(iii)Thereisnosignificant increaseinindividual orcumulative occupational radiation exposure.
Theproposedchangeswillnotresultinchangesintheoperation orconfiguration ofthefacility.
Therewillbenochangeinthelevelofcontrolsormethodology usedforprocessing ofradioactive effluents orhandlingofsolidradioactive waste,norwilltheproposalresultinanychangeinthenormalradiation levelswithintheplant.Therefore,
'herewillbenoincreaseinindividual orcumulative occupational radiation exposureresulting fromthischange.
li*}}

Latest revision as of 00:30, 4 February 2020

Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17335A362
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 12/03/1998
From:
INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17335A360 List:
References
NUDOCS 9812080050
Download: ML17335A362 (142)
v • d • e


Text

ATTACHMENT 2A TO AEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES

'ARKED TO SHOW PROPOSED CHANGES UNIT 1 REVISED PAGES 3/4 0-3 3/4 3-2la 3/4 4-38 3/4 4-40 3/4 7-15 3/4 9-1 3/4 9-13 5-6 5-7b 6-4 9812080050 981203 PDR ADOCK 05000815 P PDR

/

3 4. 0 APPLICABILITY SURVEILLANCE RE UIREMENTS

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler And Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspec-inspection and testing criteria tion and testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e., Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 endments $ 00, 107 and 108 granted extensions or cer a n su eillanck require to be p rformed n or before July 31, 1987, and til the end of e Cycle -10 refu ling outage. or these speci c surve lances der thi section, the sP cified ime interva requir d by Spe ificatio 4.0.2 w the new i ll be termin d with tiation date es blished y the s eilla ce date during the Unit 1 987 refuelin outa e.

4.0.7 en e e ann surveys anc to be perfo ed on o before pril 1, 1989, until the end of the Cyc 10-11 fueling utage. For th e speci c su eillan es under this ext sion, t p speci ed ti interv s req ired b Specifi ation 4. 2 will bq dete ned wx h the n q ini ation te establis d by the urveillance date durin the Un' 1 89 refueling 'out COOK NUCLEAR PLANT - UNIT 1 3/4 0-3 AMENDMENT NO.ggg <</gal <<144

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 14 Water Level-Low- any Stm.Gen.

Low

b. 4 kv Bus Loss of 3/Bus 2/Bus , 2/Bus 1,2,3 14 Voltage Pump Start 2/bus (Tl I A-Train B; T11D-Train A)

Valve Actuation (Both 2/bus on trains) (Tl IA 8c T11B or 2/busses Tl lc &

T11D)

c. Safety Injection 1, 2, 3 18
d. Loss of Main 1,2 18 Feedwater Pumps
7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1, 2, 3 14 Water Level-Low- any 2 Stm.

Low Gen.

b. Reactor Coolant Pump 4-1/Bus 1,2,3 19 Bus Undervoltage
8. LOSS OF POWER
a. 4 kv Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3,4 14 Voltage
b. 4 kv Bus Degraded 3/Bus 2/Bus 2/Bus I, 2, 3, 4 14 Voltage (Ttl 8 TraInlj (Ttth-TrRI'~Sj (rttA-7~:~8>

at t) - Tr~'~h) Yttb-frai~h) sub-T~t~h)

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-21a AMENDMENT$ C, ~, 153

4.4.$ 2.1 Both Reactor Vessel head vent paths shall be deaanstrated OPI',RAB least once per 18 months by:

1. Verifying the ccmaaa manual isolation valve in the Reactor vessel head vent is sealed in the open position.
2. Cycling each of the remotely operated valves in esoh path through at least one complete cycle of full travel tree the Control RocNa while in Bodes 5 or 6.

3~ Verifying floe through both of the Reactor Vessel head vent paths dur ing vaat~ operation, awhile in Bodes 5 or 6.

AeQ.lance equiraaen to demons ate the oper ility of eac eactor V el head ve path vQ,l e performed he next time e unit enters H ES 5 or 6 spec1r1 tion, and Ilying th issuance of his Technical or the app prtate pl prccednrea ee been vritten. p D. C COOK - UNIT l 3/4 4-38

4.4.$ g.2 Both suriser s~eaa space veat paths shall be deneastrated 0? at least oace pec 18 cenths byc

f. Verifying the comma aaaual isolation valvo ia the Pressurizer st04$ space vent is sealed ia the open yoaitioao Cyoliag each of the reaetely operated valves in each yath through at least oae ooaplete cycle of full travel froa tho Coatrol Rooe

~e in Hades 5 or 6.

3. Verifying flam through both of the Pressurizer steaa sycLce rent yaths 4uriag veatiag operation, ~le in }fedos 5 oc'.

illanoe req urer ants to 4 nstrate t ~ operabi y of each Pr ste space veat th Wll b perfo the next t the t eaters ES 5 oc' f loviag the ssuaaoe this Techaiy after te Plant rocedures hag@ been e'it tea. /

Speed.fkcati9, aad e appropr D ~ C o COOK 3/4 4-40 Aaaadmeat ceo.98

C OOL G V TE 0 0 ERATIO 3.7.3.1

a. At least two independent component cooling water loops shall be OPERABLE.

ML

b. At least wnce component cooling water flowpath in support of Unit 2 shutdown functions shall be available.

Specification 3.7.3.1.b - At all times when Unit 2 is in MODES 1, 2, 3, or 4.

~CT~IO V&bh Specification 3.7.3.1.a is applicable:

Vith only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 /> 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 />.

When Specification 3.7.3.1.b is applicable:

With no flowpath to Unit 2 available, 'return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12,hours and HOT SHUTDOWN .within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling .water loops shall be demonstrated OPERABLE'.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety In]ection test signal.
c. By verifying pump performance pursuant to Specification 4.0.5.
d. At least once per 18 months during shutdown, by verifying that thehcross-tie valves can cycle full travel. Pollowing cycling, the valves will be verified to be in their closed positions.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-15 AMENDMENT NO. 447, 434, 444, 164

rI I

G 0 ORO CONCE LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbol'ted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a. Either a K

.eff of 0.95 or less, which includes ffallowance a 1% Jc/k conservative for uncertainties, or

b. A boron concentration of greater than or equal to 2400 ppm, which includes a 50 ppm conservative allowance for uncertainties.

~CT~O With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes~+ and initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or its equivalent until Keff f is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLPSCE RE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall 'oe determined prior to:

a. Removing or unbolting the reactor vessel head, and
b. Withdrawal of any full length control rod in excess of 3 feet from

'its fully inserted position.

4.9.1.2 The boron concentration of, the reactor coolant system and the

~~~it~Mxi 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

0ACe. pe,r

  • The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.
  • ~ For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

D. C. COOK - UNIT 1 3/4 9-1 AMENDMENT NO.

~

~

c' ~l 3,9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

Whenever irradiated fuel is in the storage pool.

a ~ With no fuel storage pool exhaust yentilati.on system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*

b. The provisions of Specificati'ons 3.0.3 and 3.0.4 are not applicable.

'4C 4.9.12 The above required fuel storage pool ventilation system shall be demonstraied t OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

At least once per 18 months or (1) after any structural. maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.
2. Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm + 10%.

oor y e ovxfli(h lovi14n c~(aN8 ~+7 5ov

  • The crane bay roll-up door and the runua&g-room-rcrH~~oer may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool,

~ Shared system with D. C. COOK - UNIT 2.

This does not include the main load block. For purposes of this specification, a deenergi"ed main load block need not be considered a load.

D. C. COOK - UNIT 1

~ 3/4 9-13 Amendment No. 1~4

I 5.0 DESIGN FEATURES 5.6 FUELSTORA E Continued Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.

2. Region 2 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
3. Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

~

The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations,'nt+raphicalbpdepieted-i~re-5 Minimum Assembly Average Burnup in MWD/MTU =

- 22,670 + 22,220 E - 2,260 E + 149 E3 Minimum Assembly Average Burnup in MWD/MTU =

- 26,745 + 18,746 E - 1,631 E + 98.4 E3 Where E = Initial Peak Enrichment 5.6.1.2: Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Description Wt. % U-235

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) . Westinghouse 17 x 17 STD '.95 17 x 17 OFA 17 x 17 V5
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT-UNIT 1 Page 5-6 AMENDMENTSV, 436, 4N, 44&, 213

eg ons I

r QXC4.

Ac)I I oUR. P 9QMiN Q ~~~COO 1

> eeoc r

I

~

'CC'CCC:

SCHMO I

C JH ""O ABLE I OOOO L

3URN 'DCM+H rr SXO r

l OO 2.0 ~ S.O

!NGl4. - IRIPIMEHT. aU-235 CWGK i'~

6.0 ADMINISTRATIVECONTROLS

  • *""Q**'"

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must holMr-htt~eld-a-Senier-Operatm-license as specified in Section 6.2.2P..

6.4 TRAINING e t;<;t. 4 va.tig) 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

5.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited tn Operations, Technical Support, Licensing, Maintenance and Radiation Protection The PNSRC membership shall consist of at least one individual from each of the areas designated.

All members, including the Chairman and his ahemates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.

PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT-UNIT 1 Page 64 AMENDMENT49, 4B) 48K, 454) 486) 4Q) 212

ATTACHMENT 2B TO AEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES MARKED TO SHOW PROPOSED CHANGES UNIT 2 REVISED PAGES 3/4 0-3 3/4 0-4 3/4 3-11 3/4 3-20 3/4 3-30 3/4 3-31 3/4 3-34 3/4 3-44d 3/4 3-47 3/4 4-13 3/4 4-14 3/4 4-33 3/4 4-35 3/4 4-37 3/4 5-4 3/4 5"8 3/4 6-12 3/4 6-14 3/4 6-47 3/4 7-12 3/4 7-13 3/4 7-16a 3/4 7-20 3/4 8-9 3/4 8-13 3/4 8-15 3/4 9"12 5-6 5-8 6-4

3 4A APPLICABILITY SURVEILIANCE RE UIEUUKNTS

b. Surveillance Intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities xequired'y the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follow's ia these Technical Specifications:

ASME Boiler And Pressure Vessel Code and applicable-Addenda Required frequencies for terminology for inservice performing inservice inspec-ins ection and testin criteria tion and testin activities Weekly At least once per 7 days Monthly At least once per 31 days

~rterly or every 3 months At least once per 92 days Semiannually or every 6 months , At least once per 184 days Yearly or annually At least once per 366 days

'o d.

The provisions of Specification 4.0.2 axe applicable to the above

'required frequencies for performing insexvice inspection and testing activities.

Performance mctivities shall of the be above inservice inspection and testing in addition to other specified Surveillance Requirements.

e~ Nothing in the ASME Boiler and Pressure Vessel Code shall be con-stxued to supersede the requirements of any Technical Specification.

'ba, 4.0.6 en g an e e ens ons or cer n surve ances required to be per ormed gn or bef re Mar h 31, 1 86, unti the end of the Cyc~ e 5-6 efueliilg outage For'se sp cific s eillanc) under this ectio the s$ cified time in exvals equired y Speci catio 4.0.2 ill be determi ed with the ne b the urveil ance da e durin the Unit 2 1984 refu nitia )on date establis ed outa e.

4.0.7 Amendments 97 and 99 granted extensions for certa n re uired to e perform d on or be re July~1, 1988, until the end of th Cycle 6- refueling utage. Fo these h ecific s eillan es unde this sec on, the s ecified t e inte ls requir d by Speci cation 4. .2 will be determine with th new init ation te establi +ed by the surveilla ce date d ng the outage.

it 2 19 refueling COOK NUCLEAR PLANT - UNIT 2 3/4 0-3 AMENDMENT NO. 7 g, g7, 1 31

1

't

)

3 40 LXC SURVEILLANCE 4.0.8 By specific re erence to s sect on, ose surve ances which must be p rformed on or before hu

-month r 36-mo t 13, 1994, and are designed as surve lances or re ed as ou ge-related s eillan s unde the pro sions o Specifi ation 4..5) may be del ed unt the en of the cl'e 9-10 efueli outage. For these spec ic s eillanc s under this se tion, speci ied time inte ls re red by pecifica ion 4.0. will b determ ed with the ne initiat on date stablish d by the surveill ce dat during th'e Unit 2 1994 efuelin outa e.

4.0.9 By specific re erence to s sect on, ose surve ances whi.ch mus be performed on before eptemb r 7, 19 4, and a desi ted as 1 month h~eillan es may e dela d unti just pr or to re eload n the tJqit 2 Cy e 9-10 efueli outa COOK NUCLEAR PLANT - UNIT 2 3/4 0-4 AMENDMENT NO. ~, 166

T B.E 3-n O CTOR I SYST ST E 0 S V C U CHANNEL MODES IN WllICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNI ~GEE C 0 ~AT. R U R

1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. ~

S/U(1) (10) 3*, 4*, 5*

B. Undervoltage Trip N.A. N.A. S/U(1) (10) 3*, 4*, 5*

Function

2. Power Range, Neutron Flux (20 ) IM( I ) M and S/U(l) 1, 2 and
  • and Q(608)
3. Power Range, Neutron Flux, N.A. R(6) 1, 2 High Positive Rate
4. Power Range, Neutron Flux, N.A. R(6) 1, 2 High Negative Rate
5. Intermediate Range, '(6,8)

S/U(l) 1, 2 and

  • Neutron Flux
6. Source Range, Neutron Flux R(6,14) M(14) and S/U(l) 2(7), 3(7),

4 and 5

7. Overtemperature AT R(9)g 1, 2 a

W

8. Overpower AT R(9)e" 1, 2
9. Pressurizer Pressure--Low Re 1, 2 o
10. Pressurizer Pressure--High RP 1, 2

~

ll. Pressurizer Water Level--High aQ 1, 2

12. Loss of Flow - Single Loop R(8)

r>

t 0

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

7. TURBINE DRIVEN AUXILIARYFEEDWATER PUMPS fl t
a. Steam Generator Water 3/Stm. Gen. 2/Stm. 2/Stm. 1, 2, 3 14*

Level--Low-Low Gen. any Gen.

2 Stm.Gen.

b. Reactor Coolant 4-1/Bus 1, 2, 3 19*

Pump Bus Undervoltage

8. LOSS OF POWER I
a. 4 kV Bus 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14*

Loss of Voltage

b. 4 kV Bus Degraded 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14*

Voltage (Qi A - (nfl'i (T7lb TmlnBj (T2lA Tm'+Si 721 l) VIE+ Qj Tz, I D- Twi<<) T't< D-<~'<4) 9 ~ MANUAL

a. Safety Injection (ECCS) 2/train 1/train 2/train 1, 2, 3, 4 18 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray 1/train 1/train 1/tra'in 1, 2, 3, 4 18 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
c. Containment Isolation- 1/train 1/train 1/train 1, 2, 3, 4 18 Phase "A" Containment Purge and Exhaust Isolation
d. Steam Line Isolation 2/s team 2/s team 2/opera- 1, '2, 3 20 line (1 line (1 ting steam per train) per line (1 train) per train)

COOK NUCLEAR PIANT - UNIT 2 3/4 3-20 AMENDMENT NO g7 'j fgg ~

137

3/4 .. LIMI'HNGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS ACTUATING MODES IN CfiANNEL CHANNEL IEEI'RIP CHANNEL FUNCTIONAL DEVICE OPERATIONAL WHICH SURVEILLANCE FUNCTfONAL UNIT CHECK CALI RAIIDH SQUIRED

l. SAFETY INIECIION, TURBINE TRIP, FEEDWATER ISOLATION.

AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS

a. Manual Initiation Scc Functional Unit 9
b. Automatic Actuation N.A. N.A. M(2) N.A. I, 2, 3, 4 Logic
c. Containm<<nt Pressure- M(3) N.A. 1,2,3 High
d. Pressurixcr Prcssurc- N.A. I, 2, 3 Low
c. DifFerential Pressure N.A. I, 2, 3 Bctwccn Steam Lines High
f. Stcam Lue Pressure- N.A. 1,2,3 Low
2. CONTAINMENTSPRAY
a. Manual Initiation Sce Functional Unit 9
b. Automatic Actuation N.A. N.A. M(2) N.A. 1, 2, 3, 4 Logic
c. Concunmcnt Pressure- M(3) N.A. 1,2,3 High.High
3. CONTAINMENT ISOLATION
a. Phase 'A Isolation I) Manual Scc Functional Unit 9
2) From Safety N.A. N.A. M(2) N.A. 1, 2, 3, 4 Injection Automatic Actuation Logic

'. Phase B'solation I) Manual Scc Functional Unit 9

2) Automatic Actuation N.A. M(2) N.A. 1,2,3,4 Logic
3) Containmcnt S M(3) N.A. 1, 2', 3 Pressure- f{igh.

High COOK NUCLEAR PLANT-UNIT2 Pago 3/4 3-30 AMENDMENT34, 434, 4K, 158

C J

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST ~RE UlRED l

c. Purge and Exhaust Isolation I) Manual Scc Functional Unit 9-
2) Containment N.A. 1,2,3,4 Radioactivity High
4. STEAM LINE ISOLATION
a. Manual Sec Functional Unit 9
b. Automatic Actuation N.A. N.A. M(2) N.A. I, 2, 3 Logic
c. Containmcnt Pressurc- M(3) N.A. I, 2, 3 High-High
d. Steam Flow in Two N.A. I, 2, 3 Steam Lines - High Coincident with T,,

Low-Low

c. Steam Linc'Prcssurc- N.A. 1,2,3 Low S. TURBINE TRIP AND FEEDWATER ISOLATION N.A. 1,2,3
a. Steam Generator Water Level High-High
6. MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
a. Stcam Generator iVater I, 2, 3 Level - Low-Low
b. 4 kV Bus Loss of I, 2, 3 Voltage
c. Safety Injection N.A. N.A. M(2) N.A. I, 2, 3
d. Loss of Main Feed N.A. N.A. N.A. 1,2 Pumps

"%teart)vhion~~tnicaLSpcciiieatiea-4A)A Ltpplicable.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-31 AMENDMENTaI, &, 434, 434, 4W, 459, 16S

P k

0

3/4. 3.3 KOH~~OEIHC GiSTM~LTION LXKKTZSC COHDZTZOS FOE QPKLLTIQS 3.3.3.1 Tahoe spec'~~

Tha r a~~~ mcraiarz~

3.~~4 ahaU. be QPKLL'.KZ ~ ~ ~/~~~~mantas~mn ~mn~

sespo~

ahcncn W~ the )

CXEZLZZT: ha abc' Tabb< 3.~.

~~

JCXZOE:

a. V'A a non'~~ channel akaxa/a~

aespoins czcaa~ tha vaLaa shee w Table 3.M, adgnos or de~a

~ aetpo~ to Mahdi tha Xfad.t tha channel fmoperabIa.

W~ 4 boers bo  %~A one oT ncce t~~~

ezabla, rake the ~Hcelt?ftoT~

ebcnca ch@nL'e fa Tabl.a 3.~.

c. The pmvta~ of Spe~caeLana 3.0.3 cad 3.0.4 are not apylf cabLa.

4.3.3.1 Each zmLfaahan zoon" metal c1nnuaak ahaLl be as she fx'eqnencMs abner ia TabLa 4.3 3.

~i~eh Q ca1

~H4ng-osage D, C. CQOK~ 2 3/4 3 34 A$EtldQolTC )f0 ~ 43

ri V 0 0 0 G O V G V E S O ~

ClhNNEL CllANNEL c< Xuasauumr: ir ¹LE~0 ~CWCQ C 0 ri

1. Steam Generators and 4 Level 1 41 Cabinet LSI Cabinet 4 l and 2, Steam Generators 2 LSI Cabinet 2 and and 3 Lovel LSI Cabinet 4
3. Steam Generators 1 LSI Cabinet 4 and and 4 Prossure LSI Cabinet 5 Steam Generators 2 LSI Cabinet 4 and and 3 Pressure LSI Cabinet 6 5, Reactor Coolant Loop LSI Cabinet 4 and 4 Temperature (Cold) LSI Cabinet 5
6. Reactor Coolant Loop LSI Cabinet 4 and Ry )

4 Temperature (llot) LSI Cabinet 5 7, Reactor Coolant Loop LSI Cabinet 4 and 2 Temperature (Cold) LSI Cabinet 6 8., Roactor Coolant Loop LSI Cabinet 4 and 2 Temperature (llot) LSI Cabinet 6

9. Pressurizer Lovel . LSI Cabinet 3 eg 0

10.

ll.

Raactor Coolant System Pressure Charging Cross-Flow Between Units Source Range Neutron Detector (N-23)

Kiev. 587'/a LSI Cabinet gorridor LSI Cabinet 4 3

n/a R'2.

  • Cbarging Gross-1'low between Units is an instrpment common to'both Unit 1 and 2, Tbis surveillance vill only bo conducted on an interval consistent Mith Unit 1 refueling.

wu hl I

r>

BL 3- 0 OS - C Ol TORING S E AT 0 0 V U E E CJNNHEL

~CEEC

1. Containment Pressure M Reactor Coolant Outlet Temperature - Tgp) (Hide Range) 2 3

~

~ Reactor coolant Inlet Temperature - (Hide Range)

M R +

Reactor Coolant Pressure Hide RangeT<<,p M

4, M

5. Pressurizer Water Level M
6. Steam Line Pressure M R 7 ~ Steam Gei>orator Hater Level Narrow Range M R
8. BHST Water Level M R
9. Boric Acid Tank Solution Level M 10'1. Auxiliary Feedwater Flow Rate M Reactor Coolant System Subcooling Margin Monitor M 12 ~ PORV Position Indicator Limit Switches M
13. PORV Block Valve Position Indicator Limit Switches M R
14. Safety Valve Position Indicator Acoustic Monitor M R
15. Incore Thermocouples (Core Exit Thermocouples) M
16. Reactor Coolant Inventory Tracking System M(2) R(1)%'(3)P (Reactor Vessel Level Indication) 17 ~ Containment Sump Level M R 1B. Containment Hater Level M Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

(2) Hith one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

(3) Completion of channel cal'ibration for sensors to be. performed below P-12 in MODE 3.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-47 AMENDMENT NO. '9&E 9S,

~>

TABLE 4.4-2 CD n

STEAM GENERATOR TUBE tNSPECTION CD CD 7C 1ST SAMPLE. 1NSPECTlON 2ND SAMPLE lNSPECTION 3AD SAMPLE INSPECTION Saintito Sire A cauli Acticin ltcituircd Result Acriun tt'oquircd Acauli Aclion Acquucd A minunum ol C-1 Nuiie NIA NIA N/A NIA S Tubes tier S. G.

C-2 Ptua dclcclive lubca C-1 Nnne NIA NIA and lnspecl edititionat Phag'detective tubes C-1 None 2S lubes tn llus S. G. C-2 aiid initiccl aitititianat C-2 Ptug detective luliea 4S tubes ui ltws S. G.

Pcrloim action tor C-3 result ol lust samtite Pciloim aclioii lor C-3 C-3 result ol lull NIA NIA aamtite C-3 tnstiect all tuties rn Atl alber ttua S. G.. l)lug Ue S Giseic None NIA NIA locllve tubes ailil C l tnsticct 2S lubes in Same S. G.s Pcilorm ac(ian tbr cacti otlicr S. G. NIA NIA C-2 but no C-2 result ol second additional Promtll nultticallon S. G. aie to NAC pursuant C-3 to specilication Additional tnspoct all lubea in 6 9.1 S. G. ia C-3 each S. G. and pkry d elective tubes.

Prompt nolilicatlon NIA NIA lo NRC pursuant lo specilicalian G.Q.I 3

N

< Shore H la tlie number ol stcam ttaneratora tn lhe unit, and it ls lhe number ol steam tteneiatora <<specter iluitnQ Jn tnrtioctlon

C REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLVPP SYSTEM LLQCAGE L~QCAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System, leakage detection syseems shall be OPERABLE:

a. One of the containmene atmosphere particulate radioactivity or ERS-2401),

monitoring'hannels (ERS-2301

b. The containment sump level and flow monitoring system, and
c. Either ehe containmene humidity monitor or one of the containmene atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION'ith only two of the above required leakage detection systems OPERABLE, operation may coneinue for up to.30 days provided grab samples of the containmene atmosphere are obtained and analyzed at lease once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when

~

ehe required gaseous and/or particulate radioactivity monieoring channels are

~

inoperable; otherwise, be in at lease 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 wiehin ehe following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonserated OPERABLE by:

a ~ Containment atmosphere particulate and gaseous (if being used) monitoring system-perfonnance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,

b. Containmene sump level and flow monitoring syseem-performance of CHANNEL CALIBRATION ae least once per 18 months, c ~ Containmene humidiey monitor (if being used) - performance of CHANNEL CALIBRATION ae lease once per 18"months.

COOK NUCL<<R PLANT - UNIT 2 3/4 4-14 AMENDMENT NO. W, ~, 159

('/4.4 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE RE<QUIRL<MI<NTS REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION Continued With PORVs and block valves not in thc same line inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the valves to OPERABLE status or close and dc-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.

h. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 In addition to the requirements of Specification 4.0.5, each PORV shall bc demonstrated OPERABLE:

At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and At least once per 18 months by operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

c. At least once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and At least once per 18 months by performing a CHANNEL CALIBRATION of thc actuation instrumentation&

4.4.11.2 Each block valve shall bc demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.11.

4.4.11.3 Deleted.

f-'Feehnieal-Speei6eatie licable.

COOI( NUCLEAR PLANT-UNIT2 Page 3/4 4-33 AMENDMENT4W, ~, 4W, 444, 196

i t

4

~

~ ~

4.4.12.1 Both Reactor Vessel head vent paths shall be deaanstrated OPE least once per 18 months by:

Verifying the common manual isolation valve in the Reactor vessel head vent is sealed in the open position.

2. Cycling each of the remotely operated valves in each path through at least one complete cycle of fulL travel from the Control Room while in Nodes 5 or 6~
3. Verifying floe through both of the Reactor Vessel head vent paths during venting operation, awhile in Nodes 5 or 6.

Surveillan e requi nts to d nstrate the, operabilit of each eactor Ves el head ve t path be perfoH the next ime the u t ters NOD 5 or 6 fol ing the suance of Technic Sp fication, and after he appropr te Plant p cedures ha e been m'i ten.

D. C. COOK - terr 2 3/4 4-35 amencunent Wo. 65

r>

4.4.12.2 Beth Pr surizer steam space vent paths shall be demonstrated OPBKLBL at least once per 18 months by:

1 ~ Verifying the common manual isolation valve in the Pressurizer steam space vent is sealed in the open position.

Cyoling each of the reaetely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.

3 . Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.

r I

Surveill+ce requireme to demo trate the pdrability of h Pressurizer steam sp e vent pa will be formed the n time He unit en ers MODES 5 or 6 fol ing the i uance of t echnic Speoifgcation, an after th appropria Plant proc es have en writt 0.~ C. COOK - UHZT 2 3/4 4-37 Amenchnent No. 65

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2

~ ~ Each ECCS subsystem shall be demonstrated OPERABLE:

a. At 1'east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position

a. IMO-390 a. RWST to RHR a. Open
b. IMO-315 b. Low head SI b. Closed to Hot Leg
c. IMO-325 c. Low head SI c. Closed 0 to Hot Leg
d. Q-262* d. Mini flow line d. Open
e. IN-263* e. Mini flow line e. Open
f. IMO-261* f. SI Suction f. Open
g. ICM-305* g. Sump Line, g. Closed
h. ICM-306* h. Sump Line h. Closed
b. At least once per 31 days by verifying that each valve (manual, power operated or automatic} in the flow path that is not locked, sealed, or

~

other se secured in position, is in its correct position.

c. By a visual inspection which verifies that no loose debris (rags, tx'ash, clothing, etc.} is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1." For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2. Of the areas affe'cted within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

ese valves must change position during the switchover from injection to recirculation flow following LOCA.

COOK NUCLEAR PLANT - UNIT 2 3/4 5-4 AMENDMENT N0.7$ ,$ 3$

ee GENCY COR COOL G S S SURVe.ELLANCE R Cc.5.3el The

~ ~ ECCS subsystem shall be demonstrated OPERABLE per the applicable Sn~eillence Reqnizenence e= 4.5.2.Oe.

4.5.3.2 All charging pumps and safety in]ection pumps, except tne above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their elecMcal po~er supply circuits, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> vhenever the temperature of one or more of "the RCS cold legs is less than or equal to 152 F as determined at least once per hour ~hen any RCS cold leg temperature is between 152'F and 200 F.

v COOK HUCLZAR PLANT - UNXT 2 3/c& 5-8

CO SYS S URVEILLANCE E REMENTS Co tinued C ~ At least once per 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure--High-High test signal+.

d. At least once per 5 years by verifying a water flow rate of at least 20 gpm (greater than or equal to 20 gpm) but not to exceed 50 gpm (less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255 psig.

chnM~peci- re-appkkcab1e.

COOK NUCLEAR PIANT - UNET 2 ~

3/4 6-12 AMENDMENT NO. 4Sg Mf 48k) 15

CONTAINM NT SYSTEMS SURVE LANCE R UIREMENTS Continued 4.6.3. 1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOHH or REFUELING NODE at least once per IG months by:I

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b. Verifying that on a Phase B containment isolation test signal,.

each Phase B isolation valve actuates to its isolation position.

c. Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation, position.

4.6.3. 1.3 The isolation time of each power operated or automatic containment isolation valve 'shall be determined to be within its limit when tested pur suant to Specification 4.0.5

~e-pmv4~-ien~Meeh

'OOK NUCLEAR PLANT UNIT 2 3/4 6-14 AMENOMENT NO. 97, 43k 458, 165

CO A DW ARRI S G COND +0 ON 3.6.5.9 The divider barrier seal shall be OPERABLE.

With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.

VE C RE 4.6.5.9 The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:

a. Removing two divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.
b. Visually inspecting at least 95 percent of the seal's'.entire length and:

Verifying that the seal and seal mounting bolts are pro-perly installed, and

2. Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.

COOK NUCLEAR PLANT - UNIT 2 3/4 6-47 AVOND~ NO. M,

P LANT SYSTEMS 3 4 7 3 COMPONENT COOL NG WA ER S S TING COND TIO 0 OPERATION 3.7.3.1

a. At least two independent component cooling water loops shall be OPERABLE.
b. At least one component cooling water flow path in support of Unit 1 shutdown functions shall be available.

Specification 3.7.3.1.b. - At all times when Unit 1 is in MODES 1, 2, 3, or 4.

~CT ON:

When Specification 3.7.3.1.a .is applicable'.

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 /> 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 />.

When Specification 3.7.P.l.b is applicable:

3o With no flowpath & Unit 1 available, return at least one flowpath to available status ithin 7 days, or provide equivalent shutdown capabil'ity in Unit 1 and return at least e flow path to available-status within-the next 60 days, or have-Unit 1 in HOT ANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing sagety related eguipment actuates to its correct position on a Safety Infection test signal.g C'. by Verifying Pumt feepm'<~ Pung'~ % SPCt4C.Wk~ 'I,Od5.

At least once per 18 months during shutdown, verify that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.

OK NUCLEAR PLANT - UNIT 2 3/4 7-12 AMENDMENT NO. M, 4k@,

158

~ ~

0 I

1

~

C 3 4.7.4 ESSENTIAL SERVICE WATER SvSTEYt LIMITING CONDITION FOR OPERATION 3.7.4.1

a. A least two independent essential service water loops shall be OP~MI >.
b. At least one essential service water flowpath associated with support of Unit 1 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.1.a. - MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b. - At all times when Unit 1 is in MODES 1, 2, 3, or 4.

ACTION'hen Specification 3.7.4.1.a is applicable:

With only one essential service ~ater loop OPERABLE; restore at. least two loops to .

OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />'s 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 /> 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 />.

When Specification 3.7.4.l.b is applicable:

With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one flow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIRENENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

ae At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test sitnalQff

~ ~ ~ - ~ ~

~ ~

c a COOK NUCL:"4Z. PI MT - UNIT 2 3/4 7-13

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued

e. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
2. a. Verifying that on a Safety Injection Signal from Unit 1, the system automatically operates in the pressurization/cleanup mode.&
b. Verifying that on a Safety Injection Signal from Unit 2, the system automatically operates in the pressurization/cleanup mode.
3. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W. G. relative to the outside atmosphere at a system flow rate of 6000 cfm'plus or minus 10%.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

plieable.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-16a AMENDMENT&, 434, 488, 202

3/4.7 7 SNUBBERS IHITINC CONDITION FOR OP ATION 3.7.7.1 All safety-related snubbers shall be OP~~"LZ.

systems required OPERABLE in those MODES).

~CT la Pith one or more snubbex's inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> x'eplace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVE L NC RE UIR NTS

~ C 4.7.7.1 Each snubber shall be demonstrated OP~~LE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a Visual ns ectio Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-9. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-9 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No. ~.

b. Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.'Snubbers which appear inoperable as' result of visual inspections shall be classified as unacceptable and may be reclassified as acceptable for the purpose of establishing the next visual inspection interval," providing that (1) the cause of the rejection is clearly established and remedied for that COOK NUCLEAR PLANT UNIT 2 3/4 7-20 AMENDMENT NO. 492,~'-, ~ 159

ELECTRICAL POUTER SYSTEHS SHUTDOWN LIHITINC COND TIQN FOR OPERA ION 3.8.1.2 As a minimum, the following A.C. electrical power sources snail 'oe OPERABI-'ne circuit between the offsite transmission network and the onsite Class 1E distribution system, and

b. One diesel generator with:
1. A day fuel tank containing a mintuaun of 70 gallons of fuel,
2. A fuel 'storage system containing a minimum indicated volume of 46,000 gallons of fuel, and
3. A fuel transfer pump.

ACTION Pith less than the above minimum required A.C. electrical power"sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive

-reactivity changes+ until the minimum required A.C. electrical power sources are restored to OPENABLE status.

SURVEIL'LANCE RE UI EHENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.5. f

  • For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RUST is greater than the minimum required by Specification 3.1.2.7.b.2.

The COOK NUCL:"M PLANT - UNIT 2 3/4 8-9 AHENDHENT NO. 4M, Ma. 159

~ p 3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 'LECTRICALPOWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued t

b. At least once per 92 days by verifying that:
1. The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.

The specific gravity, corrected to /7'F, and full electrolyte level (fluid't the bottom of the maximum level indication mark), of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and

3. The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

At least once per 1& months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, The cell-to~ll and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material, f
3. The battery charger will supply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

At least once per 18 months, perform a battery service test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2. The battery charger will be disconnected throughout the test. The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this test~

At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops morc than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. If the bauery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.

Mte-provisions-ef-Specif cati a licable COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-13 AMENDME<NT443, 439, 4@i, 183

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1 - 250-volt D.C. bus, and 1 - 250-volt battery bank and charger associated with the above D.C. bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.8.2.4.1 The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.~

e-epplieabl ttirtnncnt

+242 X2.cLfowho4-C~wtte~~+dtargcr.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-15 AMENDMENT443, 4', 183

3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

whenever irradiated fuel is in the storage pool.

Pith no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*

b. The provisions of Specifications 3.0.3 and 3.0 ' are not applicable.

S 'RV VC R U ITS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying -hat the train operates for at least 15 minutes.
b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
1. Deleted.
2. Verifying that the charcoal adsorbers remove ) 99% of a halogenated hydrocarbon -,refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flaw rate of 30,000 cfm + 10%.

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The crane bay roll-up door and the may be opened under administrative control. during movement of fuel within the storage pool or crane. operation with loads over the storage pool.

Shared system with D. C. COOK - UNIT 1.

This does not include the main load block. For purposes of this specification, a deenergized main load block need not be considered a load.

, C. COOK - UNIT 2 3/4 9-12 Amendment No 111

5.0 DESIGN FEATURES 5.6 FUEL STORAGE Continued CRITICALITY- SPENT FUEL Continued The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations'an~mphieai~ieted=in=Rgtt~~

For Re ion 2 Stora e Minimum Assembly Average Burnup in MWD/MTU =

-22,670 + 22,220 E-2,260 E + 149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU =

-26,745 + 18,746 E- 1,631 E2 + 98.4 E3 Where E = Initial Peak Enrichment 5.6.1.2 Fuel stored in the spent fuel storage raCks shall have a nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Description Wt. % U-235

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) Westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 V5
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT-UNIT2 Page 54 AMENDMENT44, 424, 447, 4', 198

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6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff sh a ll meet or exceed!he minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (I) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must hetthuntmuohct .crater Lt specified in Section 6.2.2P.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Site Vice President/Plant Manager, or designe", on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Tcchnical Support, Licensing, Maintenance and Radiation Protection.

The PNSRC membership shall consist of at least one individual from each of the areas designated.

All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.

PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior opeiator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT-UNIT2 Page 6-4 AMENDMENT34, 447) 438, 4VR, 47$ , 197

ATTACHMENT 3A TO AEP:NRC:0433Q PROPOSED TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 1 3/4 0"3 3/4 3-2la 3/4 4-38 3/4 4-40 3/4 7-15 3/4 9-1 3/4 9-13 5-6 5-7b 6-4

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for inservice inspection and testing activities inservice ins ction and testin criteria Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

Performance of the above'inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 Deleted.

4.0.7 Deleted.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 0-3 AMENDMENT400, 43k, 444

1 f

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMIi22'I'ATION ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONALUNIT CHANNELS TO TRIP OPERABLE MODES ACTION

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS C
a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 14 Level-Low-Low any Stm.Gen.
b. 4 kv Bus Loss of Voltage 3/Bus 1,2,3 14 Pump Start 2/bus (T11A-Train B; T11D-Train A)

Valve Actuation (Both 2/bus on (T11A trains) & T11B or 2/busses T11C

& T11D)

c. Safety Injection 1, 2, 3 18'.

Loss of Main '2 1,2 18 Feedwater Pumps

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. I, 2, 3 14 Level-Low-Low any 2 Stm.

Gen.

b. Reactor Coolant Pump 4-1/Bus 1,2,3 19 Bus Undervoltage
8. LOSS OF POWER
a. 4 kv Bus Loss of 1,2,3,4 14 Voltage
b. 4 kv Bus Degraded 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 14 Voltage (TI IA-Train B; (T11A-Train B; (T11A-Train B; TI ID-Train A) T11D-Train A) T11D-Train A)

COOK NUCLEAR PLANT-UNIT1 Page 3/4 3-21n AMENDMENT$ 9, 48$ , 4'

I 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM REACTOR VESSEL HEAD VENTS SURVEILLANCERE UIREMENTS 4.4.12.1 Both Reactor Vessel head vent paths shall be demonstrated OPERABLE at least once per t8 months by:

Verifying the common manual isolation valve in the Reactor vessel head vent is sealed in the open position.

Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.

Verifying flow through both of the Reactor Vessel head vent paths during venting operation, while in Modes 5 or 6.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-38 AMENDMENT98

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS SURVEILLANCE RE UIREMENTS 4.4.12.2 Both Pressnrlacr steam space vent paths shall be demonstrated OPERABLE at least once per t8 months by:

1. Verifying the common manual isolation valve in the Pressurizer steam space vent is sealed in the open position.

Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.

3. Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.

COOK NUCLEAR PLANT-UNITI Page 3/4 440 AMENDMENT98

3/4 LIMITINGCONDITIONS I OR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

At least one component cooling water flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.1.a- MODES 1, 2, 3 and 4.

Specification3.7.3.1.b- At all times when Unit 2 is in MODES 1, 2, 3, or 4.

ACTION:

When Speciiflication3.7.3.1.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBYwithin 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 />.

When Specification3.7.3.1.b is applicable:

With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBYwithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirementsof Specification3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

By verifying pump performancepursuant to Speciftcation4.0.5.

At least once per id months during shutdown, by verifying that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.

COOK'NUCLEAR PLANT-UNIT1 Page 3/4 7-15 dhggbtDhtgbyg gttg, ggh, ddd, ddd

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITINGCONDITIONFOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

Either a K,of0.95 or less, which includes a 1% Ak/k conservative allowance for uncertainties, or A boron concentration of greater than or equal to 2400 ppm, whLh includes a 50 ppm conservative allowance for uncertainties.

APPLICABILITY: MODE 6 ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONSor positive reactivity changes" and initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or its equivalent until K,z is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm, whichever is the more restrictive. The provisions of Specification3.0.3 are not applicable.

SURVEILLANCERE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a. Removing or unbolting the reactor vessel head, and
b. Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position.

4.9.1.2 The boron concentration of the reactor coolant system and the refueling, canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

'The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.

10 For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 9-1 AMENDMENTS%

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMIPlTS 3/4.9 REFUELING OPERATIONS REFUELING OPERATIONS STORAGE POOL VENTILATIONSYSTEMh*

LIMITINGCONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool+ until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.'h
b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

At least once per 31 days by initiating fiow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.
2. Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm k 10%.

srthe crane bay roti-up door and the south door oy the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

'pd'Shared system with D. C. COOK - UNIT 2.

+This does not include the main load block. For purposes of this specification, a dewnergized main load block need not be considered a load.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 9-13

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5.0 DESIGN FEATURES 5.6 FUEL STORAGE Continued

1. Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.

Region 2 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

The equivalent reacdvtqr criteria for Region 2 and Region 3 is defined via the following equations:

For Re ion2Stora e Minimum Assembly Average Burnup in MWD/MTU =

22670+ 22220 E-2260'+ 149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU =

-26,745 + 18,746 E- 1,631 E~ + 98.4 E3 Where E = Initial Peak Enrichment I

5.6.1.2: Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Description Assembly Enrichment Wt. % U-235

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15x15 4.95
3) Westinghouse 17 x 17 STD 4.95 17x 17OFA 17 x 17 VS
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT-UNIT1 Page 54 AMENDMENT5V, 486, 448, 469, SH

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Figure 5.6-3 intentionally deleted.

COOK NUCLEAR PLANT-UNlT1 Page 5-7b AMENDMENTBi9.

6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must be qualified as specified in Section 6.2.2.g.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18. 1-1971 and 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITI'EE NSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Tcchnical Support, Licensing, Maintenance and Radiation Protection.

The PNSRC membership shall consist of at least one individual from each of the areas designated.

All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.

PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge. at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT-UNIT1 Page 64 AMENDMENT49, 6S, 4', 484) 486, 493, 212

ATTACHMENT 3B TO AEP:NRC:0433Q PROPOSED TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 2

, 3/4 0-3 3/4 0-4 3/4 3-11 3/4 3-20 3/4 3-30 3/4 3-31 3/4 3-34 3/4 3-44d 3/4 3-47 3/4 4-13 3/4 4-14 3/4 4-33 3/4 4-35 3/4,4-37 3/4 5-4 3/4 5"8 3/4 6-12 3/4 6-14 3/4 6-47 3/4 7-12 3/4 7-13 3/4 7-16a 3/4 7-20 3/4 8-9 3/4 8-13 3/4 8-15 3/4 9-12 5-6 5-8 6-4

3/4 LIMITINGCONDITIONS FOR OPERATION AND SIRVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCERE UIREMENTS

b. Surveillance Intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for inservice inspection and testing activities inservice inspection and testing criteria Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 monoths At least once per 184 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 Deleted.

4.0.7 Deleted.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 0-3 AMENDMENTVS, QV, 48k

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.0 APPLICABILITY SURVEILLANCERE UIREMENTS 4.0.8 Deleted.

4.0.9 Deleted.

COOK NUCLEAR PLANT-UNIT2 1

Page 3/4 S4 ~wuMHmm, m

TABLE4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATIONSURVEILLANCERE UIREMENTS CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONALUNIT CHECK CALIBRATION TEST RE UIRED

1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. S/U(1)(10) I, 2, 3, 4, 5 B. Undervoltage Trip Function N.A. N.A. S/U(1)(10) 1,2, 3,4',5
2. Power Range, Neutron Flux S D(2,8), M(3,8) M and S/U(1) 1,2and and Q(6,8)
3. Power Range, Neutron Flux, High Positive Rate R(6) 1,2
4. Power Range, Neutron Flux, High Negative Rate N.A. R(6) 1,2
5. Intermediate Range, Neutron Flux R(6,8) S/U(1) 1,2, and
6. Source Range, Neutron Flux R(6,14) M(14) Gild 2(7), 3(7), 4 and 5 S/U(1)
7. Overtemperature b,T R(9) M 1,2
8. Overpower hT R(9) 1,2
9. Pressurizer Pressure Low 1,2
10. Pressurizer Pressure High 1,2
11. Pressurizer Water Level High M 1,2
12. Loss of Flow-Single Loop R(8)

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONALUNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2, 3 Level Low-Low any 2 Stm. Gen. 14'.

Reactor Coolant Pump 4-1/Bus 1,2, 3 Bus Undervoltage 19'.

8. LOSS OF'POWER 4 kV Bus 3/Bus 2/Bus 1,2,3,4 Loss of Voltage 14',2,3,4
b. 4 kV Bus 3/Bus 2/Bus 2/Bus 14 Degraded Voltage P21A - Train 8; (T21A - Tnin 8; (TRIA-Tnin B; T21D - Tnin A) TZID-Train A) T21D-Tnin A)
9. MANUAL
a. Safety Injection (ECCS) 2/train 1/train 2/train 1,2,3,4 18 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray 1/train 1/train 1/train 1,2,3,4 18 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
c. Containment Isolation- 1/train 1/train 1/train 1,2,3,4 18 Phase "A" Containment Purge and Exhaust Isolation
d. Steam Line Isolation 2/steam line 2/steam line 2/operating 1,2,3 20 (1 per train) (1 per train) steam line (1 per train)

COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-20 AMENDMENTVV; 4%, 437

3/4 LIMlTINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCERE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCFIONAL UNIT CHECK CALIBRATION TEST ~ RE(EUIRED

l. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
a. Manual Initiation Sec Functional Unit 9
b. Automatic Actuation N.A. M(2) N.A. I, 2, 3, 4 Logic
c. Containment Pressure M(3) N.A. I, 2, 3 High
d. Pressurizer Pressure- N.A. I, 2, 3 Low
e. Differential Pressure N.A. I, 2, 3 Between Steam Lines High
f. Steam Linc Pressure- N.A. I, 2, 3 Low
2. CONTAINMENTSPRAY
a. Manual Initiation See Functional Unit 9
b. Automatic Actuation N.A. M(2) N.A. I, 2, 3, 4 Logic
c. Containment Pressurc- M(3) N.A. I, 2, 3 High-High
3. CONTAINMENT ISOLATION
a. Phase A Isolation I) Manual Sec Functional Unit 9
2) From Safety N.A. N.A. M(2) N.A. I, 2, 3, 4 Injection Automatic Actuation Logic
b. Phase B Isolation I) Manual See Functional Unit 9
2) Automatic Actuation N.A. N.A. M(2) N.A. I, 2, 3, 4 Logic
3) Containment M(3) N.A. I, 2, 3 Pressure- High-High COOK NUCLEAR PLANT-UNlT2 Page 3/4 3-30 AMENDMENT84, 9, 43V, 488

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION TABLE4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIONSYSTEM INSTRUMENTATION SURVEILLANCERE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL FUNCfIONAL OPERATIONAL SURVEILLANCE CHANNEL FUNCTIONALUNIT CHECK CALIBRATION TEST RHtHUIRED

c. Purge and Exhaust Isolation I) Manual See Functional Unit 9
2) Containment e N.A. I, 2, 3, 4 Radioactivity High
4. STEAM LINE ISOLATION
a. Manual See Functional Unit 9
b. Automatic Actuation N.A. N.A. M(2) N.A. I, 2, 3 Logic
c. Containment Pressure M(3) N.A. 1,2,3 High-High
d. Steam How in Two Steam M N.A. 1,2,3 Lines High Coincident with T~ Low-Low
c. Steam Line Pressure- N.A. 1,2,3 Low
5. TURBINE TRIP AND FEEDWATER ISOLATION
a. Steam Generator Water M N.A. 1,2,3 Lcvcl - High-High
6. MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS
a. Steam Generator Water N.A. 1,2,3 Level Low-Low
b. 4 kV Bus Loss of Voltage S R M N.A. 1,2,3
c. Safety Injection N.A. N.A. M(2) N.A. I, 2, 3
d. Loss of Main Feed Pumps N.A. N.A. R N.A. 1,2 COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-31 AMENDMENT%,%, 43k, 434, 4&V,

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,3 INFIRUMENTATION INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATIONMONITORING INSTRUMENTATION LIMITINGCONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCERE UIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONALTEST operations during the modes and at the frequencies shown in Table 4.3-3.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-34

TABLE4.3-6A APPENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCERE UIREMENTS 0

0 CHANNEL CHANNEL INSTRUMENT LOCATION CHECK CALIBRATION R

C O 1. Steam Generators 1 and 4 Level LSI Cabinet 1 and LSI Cabinet 4

2. Steam Generators 2 and 3 Level LSI Cabinet 2 and LSI Cabinet 4 R

I 3. Steam Generators 1 and 4 Pressure LSI Cabinet 4 and LSI Cabinet 5 R

4. Steam Generators 2 and 3 Pressure LSI Cabinet 4 and LSI Cabinet 6
5. Reactor Coolant Loop 4 Temperature (Cold) LSI Cabinet 4 and LSI Cabinet 5
6. Reactor Coolant Loop 4 Temperature (Hot) LSI Cabinet 4 and LSI ,R Cabinet 5 tA 4J 7. Reactor Coolant Loop 2 Temperature (Cold) LSI Cabinet 4 and LSI Cabinet 6 C4 Reactor Coolant Loop 2 Temperature (Hot) LSI Cabinet 4 and LSI Cabinet 6
9. Pressurizer Level , LSI Cabinet 3 M
10. Reactor Coolant System Pressure LSI Cabinet 3
11. Charging Cross-Flow Between Units Corridor Elev.

587'SI

12. Source Range Neutron Detector (N-23) Cabinet 4
  • Charging Cross-Flow between Units is an instrument common to both Unit I and 2. This surveillance will only be conducted on an interval consistent with Unit I refueling.

TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATIONSURVEILLANCERE UIREMENTS INSTRUMENT CHANNEL CHANNEL CHECK CALIBRATION

1. Containment Pressure M R
2. Reactor Coolant Outlet Temperature - Tnor (Wide Range) M R
3. Reactor Coolant Inlet Temperature - Tco~ (Wide Range) M R
4. Reactor Coolant Pressure - Wide Range M R
5. Pressurizer Water Level M R
6. Steam Line Pressure M R
7. Steam Generator Water Level - Narrow Range M R
8. RWST Water Level M R
9. Boric Acid Tank Solution Level M R
10. Auxiliary Feedwater Flow Rate M R
11. Reactor Coolant System Subcooling Margin Monitor M R
12. PORV Position Indicator - Limit Switches M R
13. PORV Block Valve Position Indicator - Limit Switches M R
14. Safety Valve Position Indicator - Acoustic Monitor M R
15. Incore Thermocouples (Core Exit Thermocouples) M Rtu
16. Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) Mu~ RP)
17. Containment Sump Level M R
18. Containment Water Level M R tnPartial range channel calibration for sensor to be performed below P-12 in MODE 3.

"Kithone train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

+Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

TABLE 4.4-2

0 0 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of S C-1 None N/A N/A N/A N/A Tubes per S.G.

C-2 Plug defective tubes and C-1 None N/A N/A inspect additional 2S tubes in this S.G.

C-2 Plug defective tubes and C-1 None inspect additional 4S tubes in this S.G.

C-2 Plug defective tubes C-3 Perform action for C-3 result of first sample C-3 Perform action for C-3 result of first sample N/A N/A C-3 Inspect all tubes in this S.G., All other plug defective tubes and S.G.s are C 1 None N/A N/A inspect 2S tubes in each other S.G.

Prompt notification to NRC pursuant to specification 6.9.1 Some S.G.s Perform action for C-2 C-2 but no result of second sample N/A N/A additional S.G.

are C-3.

Additional Inspect all tubes in each '/A N/A S.G. is C-3 S.G. and plug defective tubes. Prompt notification to NRC pursuant to specification 6.9.1.

S=3(N+n)% Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection.

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITINGCONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a1 One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or ERS-2401),

The containment sump level and flow monitoring system, and Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).

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

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, 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 />.

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONALTEST at the frequencies specified in Table 4.3-3.

Containment sump level and flow monitoring system-perfo'rmance of CHANNEL CALIBRATIONat least once per 18 months.

C. Containment humidity monitor (if being used) - performance of CHANNEL CALIBRATIONat least once per 18 months.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 4-14 AMENDMENTV8, 43k, 459

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION Continued With PORVs and block valves not in the same line inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the valves to OPERABLE status or close and de-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.

h. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.1 F 1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
b. At least once per 18 months by operating the PORV through one complete cycle of full travel during MODES 3 or 4, and
c. At least once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and
d. At least once per 18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.1 1.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.11.

4.4.1 1.3 Deleted.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 4-33 AMENDMENT45k) 458, 459, 46k, 496

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM

"'EACTOR VESSEL HEAD VENTS SURVEILLANCE RE UIREMENTS 4.4.12.1 Both Reactor Vessel head vent paths shall be demonstrated OPERABLE at least once per 18 months by:

Verifying the common manual isolation valve in the Reactor vessel head vent is sealed in the open position.

Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.

Verifying flow through both of the Reactor Vessel head vent paths during venting operation, while in Modes 5 or 6.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 4-35 AMENDMENT65

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS SURVEILLANCERE UIREMENTS 4.4.12.2 Both Pressurizer steam space vent paths shall be demonstrated OPERABLE at least once per 18 months by:

1. Verifying the common manual isolation valve in the Pressurizer steam space vent is sealed in the open position.
2. Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room while in Modes 5 or 6.
3. Verifying flow through both of the Pressurizer steam space vent paths during venting operation, while in Modes 5 or 6.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 4-37 AMENDMHNTdd

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SURVEILLANCERE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

ao At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position

a. IM0-390 RWST to RHR a. Open
b. IMO-315 b. Low head SI to Hot Leg b. Closed
c. IM0-325 c. Low head SI to Hot Leg c. Closed
d. IM0-262'. d. Mini flow line d. Open IM0-263 e. Mini flow line e. Open
f. ~ f. SI Suction f. Open ICM-306'.h.

IM0-261'.

ICM-305'l.

g. Sump Line g. Closed Sump Line h. Closed
b. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and
2. Of the areas affected within containment at the completion of each containment entry when CONTAINMENTINTEGRITY is established.

These valves must change position during the switchover from injection to recirculation fiow following LOCA.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 54 ~mnmm vs, m

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SURVEILLANCERE UIREMENTS 4.5.3.1, The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.  !

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is less than or equal to 15ZF as determined at least once per hour when any RCS cold leg temperature is between 15ZF and 200'F.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 54

.w a 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS SURVEILLANCERE UIREMENTS Continued At least once per 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure-High-High test signal.

At least once per 5 years by verifying a water flow rate of at least 20 gpm (greater thanor equal to 20 gpm) but not to exceed 50 gpm (less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255psig.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-12

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3/4 LIMrIINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3.1.2 Each containment isolation valve specified shall hc demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-14 AMENDMENTPP, age, Sgg, Sdg

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3/4 LIMH'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS DIVIDER BARRIER SEAL LIMITINGCONDITION FOR OPERATION 3.6.5.9 The divider barrier seal shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE RE UIREMENTS 4.6.5.9 The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:

Removing two divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.

Visually inspecting at least 95 percent of the seal's entire length and:

Verifying that the seal and seal mounting bolts are properly installed, and Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-47 AMENDMENTV8, 4R, 459

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS i 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.3.1 al At least two independent component cooling water loops shall be OPERABLE.

At least one component cooling water flow path in support of Unit 1 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.1.a. - MODES 1, 2, 3, 4.

Specification 3.7.3.1.b. - At all times when Unit 1 is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.7.3.1.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 /> 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 />.

When Specification 3.7.3.1.b is applicable:

With no flowpath to Unit 1 available, return at least one flowpath to available status within 7 days, or provide I equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test I

signal.

c. By verifying pump performance pursuant to Specification 4.0.5.
d. At least once per 18 months during shutdown, verify that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-12 AMENDMENT%, 44G, 43k, 458

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.4.1

a. At least two independent essential service water loops shall be OPERABLE.
b. At least one essential service water flowpath associated with support of Unit 1 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.1.a. - MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b. - At all times when Unit 1 is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.7.4.1.a is applicable:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBYwithin 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 />.

When Specification 3.7.4.1.b is applicable:

With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one fiow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-13 AMENDMENT%, 446, 48k, 458, 459

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCERE UIREMENTS Continued

e. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
2. a. Verifying that on a Safety Injection Signal from Unit 1, the system automatically operates in the pressurization/cleanup mode.
b. Verifying that on a Safety Injection Signal from Unit 2, the system automatically operates in the pressurization/cleanup mode.
3. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W. G. relative to the outside atmosphere at a system flow rate of 6000 cfm plus or minus 10%.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon i refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-16a AMENDMENTW, m, m, am

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.7 SNUBBERS LIMITINGCONDITION FOR OPERATION 3.7.7.1 All safety-related snubbers shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREMENTS 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

Visual Ins ction Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-9. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-9 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No.

156.

Visual Ins ction Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified as acceptable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-20 AMENDMENTue, m, 1, m

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS ELECTRICALPOWER SYSTEMS SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.1.2 As a minimum, the followingA.C. electrical power sources shall be OPERABLE:

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and One diesel generator with:

1. A day fuel tank containing a minimum of 70 gallons of fuel.
2. A fuel storage system containing a minimum indicated volume of 46,000 gallons of fuel, and
3. A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

ACI'ION:

Will less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes* until the minimum requiredA.C. electrical power sources are restored to OPERABLE status.

SURVEILLANCERE UIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1 1.2 except for

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requirement 4.8.1 1.2.a.5.

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For purpose of this specification, addition of'water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-9 AMENDMENTARAN, 444 459

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS SURVEILLANCERE UIREMENTS Continued At least once per 92 days by verifying that:

The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.

The specific gravity, corrected to 77'F, and full electrolyte level (fluid at the bottom of the maximum level indication mark), of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

C. At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with antieorrosion material,
3. The battery charger will supply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

At least once per 18 months, perform a battery service test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2. The battery charger will be disconnected throughout the test. The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this test.

e. At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. If the battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-13 AMENDMENT448, 489, 466, 46

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3/4.0 LIMI'rINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1 - 250-volt D.C. bus, and 1 - 250-volt battery bank and charger associated with the above D.C. bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCERE UIREMENTS 4.8.2.4.1 The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2. I COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-15 AMENDMENTS, ae, m

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.9 REFUELING OPERATIONS STORAGE POOL VENTILATIONSYSTEM" LIMITINGCONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storagepool+ until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status'.

The provisions of Speciflcations3.0.3 and 3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

At least once per IS months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.
2. Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfmk 10%.

'The crane bay roii-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

"Shared system with D. C. Cook - Unit 1.

+This docs not include the main load block. For purposes of this specification, adeenergized main load block need not be considered a load.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 9-12 AMENDMENT444

5.0 DESIGN FEATURES 5.6 FUELSTORAGE Continued CRITICALITY-SPENT FUEL Continued The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations: I For Re ion2Stora e Minimum Assembly Average Burnup in MWD/MTU=

-22,670+ 22,220E-2,2608 + 149 E3 For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU=

-26,745+ 18,746 E - 1,631 E' 98.4 Ei Where E = Initial Peak Enrichment 5.6.1.2 Fuel stored in the spent fuel storage racks shaH have a nominal fuel assembly enrichment as follows:

Description Maximum Nominal Fuel Assembly Enrichment Wt.  % U-235

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15x 15 4.95
3) Westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17x17V5
4) Exxon/AN F 17x 17 4.95 COOK NUCLEARPLANT-UNIT2 Page 54 AMENDMENT4k, 49k, 447, 483, 498

5.0 DESIGN FEATURES Figure 5.6-3 intentionally deleted.

COOK NUCLEAR PLANT-UNIT2 Page 5-8

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6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff sh all meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must be qualified as specified in Section 6.2.2.g.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Plant Managers or Department Superintendents. The membership shall represent the functional areas of the plant, including, but not limited to Operations, Technical Support, Licensing, Maintenance and Radiation Protection.

The PNSRC membership shall consist of at least one individual from each of the areas designated.

All members, including the Chairman and his alternates, the members and their alternates, shall be designated by the Site Vice President/Plant Manager.

PNSRC members and alternates shall meet or excccd the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License. The operations individual must hold or have held a Senior Operator License or have been certified for equivalent senior operator knowledge at Cook Nuclear Plant or a similar reactor. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT-UNIT2 Page 6-4 AMENDMENT34, 447, 438, 4', 4VS, 493

ATTACHMENT 4 TO AEP:NRC:0433Q 4

EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION to AEP:NRC:0433Q Page 1 Evaluation of Si nificant Hazards Consideration The Licensee has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:

1. involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated;
2. create the possibility of a new or different kind of accident from any previously analyzed; or
3. involve a significant reduction in a margin of safety.

The Licensee proposes to make administrative changes to several technical specifications (T/S) for Donald C. Cook Nuclear Plant unit 1 and unit 2. The proposed changes include: (1) revising boron sampling requirements in mode 6; (2) deleting a reference to obsolete equipment in a footnote; (3) deleting a redundant figure; (4) correcting a reference to another requirement; (5) deleting obsolete notes; (6) adding to surveillance requirements; (7) clarifying instrumentation configuration; and (8) correcting typographical errors. These changes are proposed to remove obsolete information, provide consistency between unit 1 and unit 2, provide consistency with the Standard Technical Specifications, provide clarification, and correct typographical errors.

The determination that the criteria set forth in 10 CFR 50.92 are met for this amendment request is indicated below.

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed change for boron sampling requirements in mode 6 does not affect the probability of a fuel handling accident.

The unlikely event of a fuel assembly being misloaded is independent of the sampling frequency for fuel pool boron concentration. It has no impact on the event initiator, which is a human error while positioning a fuel assembly. The change has no impact on the* assumptions for a fuel handling accident. The boron concentration requirement is not changed; there is sufficient boron in the fuel storage pool to maintain k,qq below 0.95 to preclude an inadvertent criticality.

Therefore, the consequences of the accident will be mitigated as previously evaluated. The 72-hour maximum interval between samples is maintained. Operating experience has shown 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to be adequate. Removing the additional limitation of sampling at least three times per week would allow the sample to be collected two or three times per week, consistent with the maximum 72-hour interval. This is acceptable because boron concentration changes occur slowly due to the large

1 to AEP:NRC:0433Q Page 2 volume of water in the system and relatively small volumes of dilution sources. The consequences are not increased because there are no changes to the spent fuel, shielding (water), or systems used to mitigate the consequences of an accident.

Additionally, there is no change in the types or significant increase in the amounts of any effluents released offsite.

Deleting the redundant figure for equivalent reactivity criteria for regions in the spent fuel storage racks does not impact the storage requirements because the equations provide equivalent requirements. The unlikely event of a fuel assembly being misloaded is independent of the characteristics of the spent fuel in the pool. It has no impact on the event initiator, which is a human error while positioning a fuel assembly. The change has no impact the assumptions for a fuel handling accident because the fuel storage requirements are not changed. The consequences of an accident are not increased because the fuel storage requirements are not changed and no other changes are made to systems that mitigate the consequences of an accident.

The proposed changes to correct a reference to another requirement, delete obsolete notes, revise the name of drumming room roll-up door, and correct typographical errors are considered administrative. The reference leads to a section that no longer exists; the proposed change corrects the error. The notes permitted exceptions to requirements, and they are no longer required. The normal requirements have applied since the provisions expired. Deleting them eliminates extraneous information. The revised description of the door reflects the current use of the installed door.

Correcting the typographical errors improves readability. The corrections are not intended to change the meaning. These changes do not affect accidents described in the UFSAR.

Adding new surveillance requirements to test the unit 2 pump performance pursuant to T/S 4.0.5 does not affect accident initiators or precursors. The change reflects ASME code requirements. Including the requirements in the corresponding section provides assurance that the pumps will operate as assumed in the accident analyses. As such, the probability and 'onsequences of previously evaluated accidents is unchanged.

The proposed change to the description of instrumentation configuration is considered administrative because the configuration had been reviewed and approved by the NRC Staff, as documented in the Safety Evaluation Report for amendment 39 for DPR-58 and amendment 22 for DPR-74. There are no changes to the actual plant configuration. The change is intended to describe the installed equipment more clearly. The change does not affect the probability and consequences of previously evaluated accidents because the equipment is installed and operated as described in the correspondence related to the previous amendments.

Based on this review, changes do not involve it a is significant concluded that the proposed increase in the

L.

Attachment 4 to AEP:NRC:0433Q Page 3 probability of occurrence or consequences of an accident previously evaluated.

2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated' The proposed changes remove obsolete information, provide consistency between unit 1 and unit 2, provide consistency with the Standard Technical Specifications, provide clarification, and correct typographical errors. These changes are considered administrative because they do not affect the design or operation of any system, structure, or component in the plant ~ The accident analysis assumptions and results are unchanged. No new failures or interactions have been created. Based on this review, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
3. Does the change involve a significant reduction in a margin of safety?

The proposed changes are considered administrative in nature.

They do not affect any safety limits or T/S parameter limits.

The proposed changes do not introduce new equipment, equipment modifications, or new or different modes of plant operation.

These changes do not affect the operational characteristics of any equipment or systems. Based on this review, concluded that no reduction in the margin of safety will it is occur as a result of the changes.

'n summary, based upon the above evaluation, the Licensee has concluded that these changes involve no significant hazards

'onsideration.

ATTACHMENT 5 TO AEP:NRC:0433Q ENVIRONMENTAL ASSESSMENT

to AEP:NRC:0433Q Page 1 Environmental Assessment The Licensee has evaluated this license amendment request against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. The Licensee has determined that this license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) . This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria.

(i) The amendment involves no significant hazards consideration.

As demonstrated in attachment 4, this proposed amendment does not involve any significant hazards consideration.

(ii) There is no significant change .in the types or significant increase in the amounts of any effluent that may be released offsite.

As documented in attachment 4, there will be no change in the types or significant increase in the amounts of any effluents released offsite.

(iii) There is no significant increase in individual or cumulative occupational radiation exposure.

The proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant.

Therefore, 'here will be no increase in individual or cumulative occupational radiation exposure resulting from this change.

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