View source for TXX-8877, Forwards Draft Rev 0 to Comanche Peak Steam Electric Station Tech Spec Improvement Program Tech Spec Requirements, Per NRC Rev 4a of Sts,For Review

{{Adams
| number = ML20206H605
| issue date = 11/17/1988
| title = Forwards Draft Rev 0 to Comanche Peak Steam Electric Station Tech Spec Improvement Program Tech Spec Requirements, Per NRC Rev 4a of Sts,For Review
| author name = Counsil W
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000445
| license number = 
| contact person = 
| document report number = TXX-88779, NUDOCS 8811230248
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 68
}}

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                                                        - -                             Log
* TXX-88779 L       4                       File > 10014
                                                        =       r                               916 clo Ref i 10CFR50.36 TUELECTRiC November 17, 1988
            $$NN, U. S. Nuclear Regulatory Commission Attn: Docutaent Control Desk
          . Washington, D.C. 20555

==SUBJECT:==
' COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 CPSES TECHNICAL SPECIFICATION IMPROVEMENT PROGR9i Gentlemen:
As you are aware, the NRC and the nuclear industry have recently recognized the benefits of improved Tech'11 cal Specifications and efforts are currently underway to develop and implement new Standard Technical Specifications which are reflective of the philosophy. Due to the unavailability of the new Standard Technical Specifications (STS), TV Electric must proceed with development of the CPSES Uni'. 1 Technical Specifications based on the NRC's Revision 4a of the STS. Our development efforts are being proposed for the CPSES Technical Specifications. These enhancements include the relocation of certain Technical Specifications, including the CPSES Technical Specification Improvement Program (TSIP).
The attachment to this letter provides a copy of the draft CPSES TSIP l           Technical Requirements. These are being provided to allow consideration by the NRC technical c.aiewers, as appropriate, during the "Proof and Review" stage of the Technical Specification approval procesc.
Very tru                                 yours, Rh W. G. Counsil RWH/gj Attachment c - Mr. R. D.inspectors, Resident   Martin, Reg.*on CPSES (3          IVco(1 copy))
Mr. R. F. Warnick, NRC (1 cop ) pies Mr. J. H. Wilson, NRC (1 copy Mr. Bob Giardina, NRC (1 copy M
0811230240 001117       5 PDR    ADCCKOSOOg4 ne sons o u surer ian can. raw n.w                                                                                   Ilq

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DRAr7 CPSES TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM (TSIP)
TECHNICAL REQUIREMENTS Rev. O

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ATTACHMENT 1                    DRAFT CPSES TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM INDEX TECHNICAL REQUIREMENT NUMBER                                        SYSTEM / TITLE           REVISION (Related Tech Spec if required) 1.1      (3/4.3.1)          Reactor Trip Response Time             0 1.2      (3/4.3.2)          ESF Actuation Response Time            0 1.3                         Moveable Incore Detection System       0             f 1.4                         Seismic Instruments                    0            '
1.5                         Meteorological Instrumentation         0            .
1.6                         Loose Parts Detection System           0 2.1      (3/4.4.6.2)        RCS Pressure Isolation Valves          0 3.1      (3/4.6.3)          Containment Isolation Valves           0 4.1       (3/4.7.9)          Snubbers                               0 4.2                          Sealed Source Contamination            0 5.1       (3/4.8.4)          Containment Penetration Conductor      0 Overcurrent Protection Devices i
i Rev. 0
                                                                                                                    - = , .

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  .T ATTACHMENT 1                                                   DRAFT l
TECHNICAL REQUIREMENT 1.1 REACTOR TRIP RESPONSE TIME NOTE:            This Technical Requirement contains the Reactor Trip Response Time Table. Although the CPSES Technical Specification is repeated here, in part, care must be taken not to overlook Technical Specification requirements.
i 1.1-1                                                      Rev. 0

4 ATTACHMENT 1                 DRAFT 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1       As a minimum., the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with REACTOR TRIP SYSTEM RESPONSE TIMES within their limits.
APPLICABILITY:     As shown in Table 3.3-1.
ACTION:                                                                       V)
As shown in Table 3.3-1.                                                      y SURVEILLANCE REQUIREMENTS N  <
                                                                        ~
O 4.3.1.1     Each Reactor Trip System instrumentation channel and interlock    b and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentatior. Surveillance 7
Requirements specified in Table 4.3-1.                                       g 4.3.1.2     The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its li:mit at least once per 18 months. Each test shall include at least one train such that both N
trainc are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months      g where N is the total number of Jedundant channels in a specific Reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.
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1.1-2                    Rev. O l

ATTACHMENT 1                                        DR L"I Technical Requirement 1.1 Table 1.1.1 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT                                                            RESPONSE TIME
: 1. Manual Reactor Trip                                                   N.A.
: 2. Power Range, Neutron Flux
* f 0.5 second*
: 3. Power Range, Neutron Flux High Positive Rate                                                    N.A.
: 4. Power Range, Neutron Flux, High Negative Rate                                                   f 0.5 second*
: 5. Intermediate Range, Neutron Flux                                      N.A.
: 6. Source Range, Neutron Flux                                           f 0.5 second*
: 7. Overtemperature N-16                                                 f 7 seconds *f
: 8. Overpower N-16                                                       f 7 seconds *#
: 9. Pressurizer Pressure-Low                                             f 2 seconds
: 10. Pressurizer Pressure-High                                            1 2 secends
: 11. Prescurizer Water Level-High                                            N.A.
i
* Neutron / gamma detectors are exempt from responsa time testing.                        Response time of the neutron / gamma flux signal portion of the channel shall be measured from detector oucput or input of first electronic component in a channel.
        / Response time includes the thermal well response time.
1.1-3                                        Rev. 0
                                                           . _ - _ - _ - _ . . _ .     ~___ - -

      ?
   *s ATTACHMENT 1                                                                DRAFT Technicel Requirement 1.1 (continued)
Table 1.1.1 REACTOR TRIP SYSTEM INSTRUMFNTATION RESPONSE TIMES FUNCTIONAL UNIT                                                                                    RESPONSE TIME
: 12. Reactor Coolant Flow-Low
: a. Single Loop (Above P-8)                                                               < [1] second
: b. Two Loopo (Above P-7 and below P-8)                                                  ][ [1] second
: 13. Steam Generator Water tevel--Low-Low                                                       < [2] seconds
: 14. Undervoltage - Reactor Coolant Pumps                                                       j[ [1.5] seconds                                                                      l
: 15. Underfrequency - Reactor Coolant Pumps                                                     j; [0.6) second
: 16. Turbine Trip
: a. Low Fluid Oil Pressure                                                                  N.A.
: b. Turbine Stop Valve Closure                                                              N.A.
: 17. Safety Injection Input from ESF                                                              N.A.
: 18. Reactor Trip System Interlocks                                                               N.A.
19,   Reactor Trip Breakers                                                                        N.A.
: 20. Automatic Trip and Interlock Logic                                                           N.A.
BASES 1.1   REACTOR TRIP SYSTEM RESPON5T YlMES T*_s bases for the Reactor Trip System are contained in the CPSES Technical Specifications. The measurement of response time at the specified 4
frequencies provides assurance that the Reactor trip actuation associated I
with each channel is completed within the time limit assumed in the safety j                 analyses. No credit was taken in the analyses for those channels with response times indicated as not appifcable. Response time may be demonstrated by any snries of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.                       Sensor response time verification may be demonstrated by eithert (1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response time.
                                                                                                                                                                                                        +
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1.1-4                                                                 Rev. O t
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4 ATTACHMENT 1                   DRAFT-            i TEChdICAL REQUIREMENT 1.2 ESF /MTUATION SYSTEM RESPONSE TIME NOTE:     This Technical Requirement contains the ESF Actuation System Response Time Table. Although the CPSES Technical Specification is repeated here, in part, care must be taken not to overlook           ,
Technical Specification requirczents.                                   ,
                                                                                                       ?
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1.2-1                      Rev. 0

s ATTACHMENT 1                   DRAFT INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTDi INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2        The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-2 shall be OYERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-3 and with ESF RESPONSE TIMES within their limit value.
APPLICABILITY:       As shown in Table 3.1-2.
ACTION:
: a. With an ESPAS Instrumentation or Interlock Trip Setpoint trip less conservative than the value shown in the Trip Satpoint column but more consersative than the value shown in the Allowable Value column of Table 3.3-3, adjust the Setpoint y  a consistent with the Trip Setpoint value.                           O
: b. With an ESFAS Instrumentation or Interlock Trip Setpoint less      amp conservative than the value shown in the Allowable Value columns
* of Table 3.3-3, either:
O mae
: 1.      Adjust- the Setpoint consistent with the Trip Setpoint     O value of Table 3.3-3, and determine within 12 hours that   g Equation 2.2-1 was satisfied for the affected channel, or  m
: 2.      Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3-2 until the    @
channel is restored to OPERABLE status with its Setpoint  g adjusted consistent with the Trip Setpoint value.
g Equation 2.2-1                        Z+R+S < TA
                                                                 -                  D mee Where
                                                                                    ),
Z = The value from Column Z of Table 3.3-3 for the affected        b channel,                                                      @
F+
R = 'Be "as found" value (in percent span) of rack error for the   ***
affected channel,.                                            D S - Either the "as found" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 3.3-3 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-3 for the affected channel,
: c. With ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-2.
1.2-2                       Rev. O

ATTACHMENT 1              DRAFT INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.3.2.1    Each ESFAi instrumentation channel and interlock and the automatic actuation logic and relays shali Le demonstrated OPERABLE by performance of the E.1FAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2    The ENGINEERED SAFETY FEATURES RESFONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 monthu. Each test. shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all chanr.els are tested at least once per N times 18 months where N is the total number of redundant n annels in a specific ESFAS function as shown in the "Total No. of Channels" column of Table 3.3-2.                    y G
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1.2-3                  Rev. O

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4 ATTACHMENT 1                       DRAFT Technical Requirement 1.2 TABLE 1,2.1 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION                      RESPONSE TIME IN SECONDS  ,
: 1. Manual Initiation
: a. Safety Injection (ECCS)       ,     . N.A.
4
_                                   r
: b. Containment Spray (Phase "L"                                      [
Isolation and Containment Vent Isolation)                               N.A.                      i
: c. Phaae   "A" Isolation (Containment Vent Isolation)                          N.A.
: d. Steam Line Isolation                    N.A.                       ,
: e. Feedvater Isolation (SI)                N.A.                      L i
: f. Auxiliary Feedvater (SI)                N.A.                      !
l               g. Station Service Water (SI)              N.A.                      ,
: h. Component Cooling Water (SI)            N.A.                       l l
: i. Control Room Emergency I
Recir- 21stion (SI)                     N.A.
: j. Reactor Trip                            N.A.
,               k. Emergency Diesel Generator
,                    Operation                               N.A.
: 1. Essential Ventilation Systems (SI) N.A.
;              m. Turbine Trip                            N.A.                       ,
1        2. Containment Pressure--High-1 l
: a. Safety Injection (ECCS)                 I27(1.5a)/12(4,5b)        ,
: b. Reactor Trip                            f2
;              c. Feedvater Isolation                     f 6.5                     l J. Phase   "A"  Isalation                   i 17( }/27(               ;
!              e. Containment Ventilation Isolation N.A.                              [
l l
l 1.2-4                       Rev. O I

a.
ATTACHMENT 1                                                         LRAFT Technical Requirement 1.2 (continued)
TABLE 1.2.1 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION                                                        RESPONSE TIME IN SECON S
: f. Auxiliary Teodwater                                                        f 60
: g. Station Service Water                                                      N.A.
: h. Component Cooling Water                                                    N.A.
: 1. Essential Ventilation Systems                                              N.A.
,               J. Emergency Diesel Generator i
Operation                                                                  f 12
: k. Turbine Trip                                                               N.A.
: 1. Control Room Emergency Recirculat'.on                                                             N.A.
: m. Containment Spray Pump (7)                                                 f 17/27
: 3. Pressurizer Pressure--Lov
: a. Safety Injection (ECCS)                                                    f27(1,5a)/12(4.5b)
: b. Reactor Trip                                                               f2 l               c. Feediater Isolation                                                        f7
: d. Phase "A" Isolation                                                        I 17( )/27( }
: e. Containment Ventilation Isolation f5(0)
: f. Auxiliary Feedwater                                                         ( 60
: g. Station Service Water                                                      N.A.
: h. Component Cooling Water                                                    N.A.                        ;
: i. Essential Ventilation Systems                                              N.A.
J. Emergency Diesel Cenorator Operation                                                                  1 12
: k. Turbine Trip                                                               M.A.
: 1. Control Room Emergeucy Recirculation                                                              N.A.
: m. Containment Spray Pump (7)                                                 f17/27 1.2-5                                                             Rev. 0

ATTACHMENT A                                                       DRAFT Technical Reauire . , ._ ,'; (continued)
TABL.
ENGINEERED SAFETY FEATsRES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION                    RESPONSE TIME IN SECONDS 4     Steam Line Pressure--Lov
: a. Safety Injection (ETCS)                                                                  ' }
1 22( .5b)/12
: k. Reactor Trip                            i3
: c. Feedwater Isolation                    16.5
: d. Phase "A" Isolation                     i 17I }/27(I)
: e. Containment Ventilation Isolation                              N.A.
: f. Auxiliary Feedwater                    1 60 t
: g. Station Service Water                  N.A.
: h. Component Cooling Water                N.A.
: i. Essential Ventilation Systems          N.A.
J. Emergency Diesel Generator Operation                               i12
: k. Turbine Trip                           N.A.
: 1. Control Room Emergency Recirculation                          N.A.
: a. Containment Spray Pu p (7)              i17/27                                                      s
: n. Steam Line Isolation                      6.5                                                     -
: 5. Containment Pressure--High-3
: a. Containment Spray Puup-                 17(
: b. Phase "B"  Isolatlon                   N.A.
: 6. Containment Pressur6 -High-2 Steam Line Isolation                    16.5
: 7. Steam L!ne Pressure - Negative Rate-High Steam Line Isolation                    17 1.2-6                                                           Rev. O

O,-
ATTACHMEET 1                     DRAFT Technical Requirement 1.2 (continued)
TABLE 1.2.1 ENGINEERED SAFETY FEATURES RESPONSE TIMES             !
INITIATION SIGNAL AND FUNCTION                   RESFDNSE TIME IN SECONDS
: 3. Steam Generator Water Level - High-High
: c. Turbine Trip                          N.A.
: b. Feedwater Isolation                   f 11
: 9. Steam Generator Water Lavel - Low-Low L    Motor-Driven Auxiliary                                         ~
Taedwater Pumps                       1 60
: b. Turbint-Driven Auxiliary                                       f Feedwater Pump                        f 60
: 10. Loss,-of-Offsite Power Auxilia y Feedvater                   N.A.
: 11. Trip of Ali Main Feedwater Pumps All Auxiliary Feedwater Pumps         N.A.
1       RWST Level - Low-Low Coincident with Safety Icjection AutosAtic Initiation of ECCS          ~
                                                                                   < 30 Switchover to Containment Sump
$                              . 3. Loss of Power (6.9 KV Safeguards System Undervoltage)
: a. Of fsite Source Undervoltage          f[later)
: b. Bus Undervoltage                      f[later]
1,2-7                        hev. 0 b s'                       .a                           A -

s ATTACINENT 1                    DRAFT Technical Requirement 1.2 (cortinued)
TABLE 1.2.1 TABLE NOTATIONS (1)     Diesel generator starting snd sequence loading delays included.
(2)     Diesel generator starting delay noj:, included. Offsite power available.
(3)     Diesel generator sesrting delay included. RHR pumps not included.
(4)      Diesel generator starting and sequence loading delays not included. RHR pumps not included.
(5)      Response Time Limit includes opening of injection path valves. Following additional time is allowed for completion of the transfer of the pump suction from the VCT to the RWST a)   10 secs b)   15 secs (6)      Includes containment pressure relief line isolation only.
(7)      Response Time Limit is up through pump breaker closure only. Both times shown include sequencer loading delays and the larger number also includes diesel generator starting delay.
BASES 1.2    ENGINEERED SAFETY FEATURES ACTUATION SYSTEM RESPONSE TIMES The bases for ths Engineered Safety Features Actuation System are contained in the CPSES Tecnnical Specifications. The measurement of response time at the specified frequencies provides assurance that the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response t ^ ts indicated as not applicable. Response time may be demonstrated by any serios of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total a.hannel response time as defined. Sensor response time varification may be demonstrated by either        (1) in place, onsite, or offsite test meacurements, or (2) utilizing replacement sensors with certified response time.
1.2-8                       Rev. 0

ATTACHMENT I                                                                     DRAFT TECHNICAL REQUIRENENT 1.3 MOVABLE IyCORE DETECTORS OPERABILITY CRITERIA 1.3 The Movable Incore Detection System shall be OPERABLE with:
: 4. At least 75% of the detector thimbles,
: b. A minimum of two detector thimbles per core quadrant, and
: c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.
APPLICABILITY:       When the Movable Incore Detection System is used fort
: a. Recalibration of the Excore Neutron Flux Detection System, or
: b. Monitoring the QUADRANT POWER TILT RATIO, or
: c. Measurement of     H F q(Z) and F,y, COMPENSATORY MEASURES:
With the Movable Incore Detection System inoperable, do not uie the system for the above applicable monitoring or calibration functions.
TEST / INSPECTIONS rego:r ed, 1.3 TheMovableIncoreDetectionSystemshallbe[demonstratedOPERABLE within 24 hours prior to use by irradiating each detector and determining the acceptability of its voltage curve when4rsquired fort we s yte.n is
: a. Recalibration of the Excore Neutron Flux Detection System, or
: b. Monitoring the QUADRANT POWER TILT RATIO, or
: c. Keasurement of F H. Fq(Z) and F BASES                                                                                                                            __
l.3 MOVABLE INCORE IsETECTO'RI~
The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensure's that the measurement.s obtained f rom use of this aystem accurately represent the spatial neutron flux distribution of the core. The OPERABI'ITY of this system is demonstrated by irradiating each detector used and deteraining the acceptability of its voltage curve.
For the purpose of measuring F Quarter-core flux taaps, asedinWCb-8648, def9n(Z) or JuneFf a1976, full incore                              may be flux         used map in    is use recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or sywmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when c..e Power Range channel is inoperable.
1.3-1                                                                        Rev. O t                                                          ~

M ACHMENT 1                                                DRAFT TECHNICAL REQUIREMENT 1.4 SEISMIC INSTRUMENTATION i
OPERA 3ILITY CRITZRIA i
)           1.4 The seismic monitoring instrumentation shown in Table 1.4.1 shall be OPERABLE.
APPLICABILITY: At ell times.
n.
COMPENSATORY MEASbRES:
: a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to CPSES Technical Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.
tests / INSPECTIONS 1.4.1        Each of the above eequired seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK.
CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies sl.own in Table 1.4.2.
1.4.2        Each of the above required seismic monitoring inr,trvaents which is accessible during power operations and which is actuated during a seismic event greater than or equal to 0.013 shall be rest; red to OPERABLE status within 24 hours and a CHANNEL CALIBRATION performed within 15 days following the seismic event.
Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shell be prepared end submitted to the Commission pursuant to CPSES Technical Specification 6.9.2 within 14 days describing tha magnitade, frequency spectrum, and resultant effait upon facility features important to safety.
1.4.3        Each of the above seismic monitoring instruments which is actuated during a seismic event greater than or equal to 0.0lg but is not accessible during power operation shall be restored to OPERA?'.E status and a CRANNEL CALIBRATION performed the next time the plant enters MODE 5 or below. A supplemental report shall then be prepared and submitted to the Commission within 14 days pursuant to CPSES Technical Specification 6.9.2 describing the additional data from these instruments.
1.4-1                                               Rev. O

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ATTACHMEFT 1                   DRAFT TECHNICAL REQUIRENDIT 1.4 TABLE 1.4.1 SEISMIC MONITORING INSTRUMENTATION MINIMUM        !
INSTRUMENTS l
INSTRUMENTS AND SENSOR LOCATIONS                         OPERABLE       I
: 1. Triaxial Time-History Accelerographs
: a. Accelerometer-Fuel Building                       1          ,
: b. Accelerometer-Containment                         1
: c. Accelerometer-Electrical Manhole                  1          .
: d. Seismic Trigger-Fuel Building                     1          i
;                           e. Recorder Unit. SMA-3                              1
: f. Playback Unit, SMP 1                              1
: 2. Triaxial Peak Accelerographs
: a. Pressurizer Lifting Tr*2nion                     1
: b. Reactor Coolant Piping                           1 i                           c. CCW Heat Exchanger                               1
                      .1    Triaxial Seismic Switch 1
Fuel Building                                          1*
: 4. Triaxial Response-Spectrum Recorders
!                           a. Fuel Building                                    I
: b. neactor Blds. Internal Structure                 1
: c. Safeguards Building                              1 1
: 5. Response Spectrum Annunciator                          18
                      ^With control room indication.
1 i
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ATTACHMENT 1                                                                                               DRAFT TECHNICAL REQUIREMENT 1.4 TABLE 1.4.2 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG
* F                                                                                                                                                                                                                                       CHANNEL CHANNEL      CHANNEL                                                                            OPERATIONAL INSTRUMENTS AND SENSOR LOCATIONS                                                                      __ CHECK , CALIBRATION                                                                               TEST
: 1.                          Triaxial Time-History Accelerographs
: a. Accelerometer-Fuel Building                                            M                                        R                                                        SA
: b. Accelerometer-Containment                                              M                                       R                                                         SA 1                                                            c. Accelerometer-Electrical Manhole                                       M                                       R                                                         SA
: d. Seismic Trigger-Fuel Building                                          M                                       R                                                         SA
: e. Recorder Unit, SHA-3                                                   M                                       R                                                         SA
: f. Playback Unit, SMP-1                                                   M                                       R                                                         SA
: 2.                         Triaxial Peak Accelerographs
: a.      Pressurire? Lif ting Trunion                                          N.A.                                     R                                                         N.A.
: b.       Reactor Coolant Piping                                                N.A.                                     R                                                         N.A.
j                                                          c.      CCW Heat Exchanger                                                    N.A.                                    R                                                          N.A.
: 3.                        Triaxial Scismic Switch Fuel Building **                                                                M                                     R                                                           SA j                              4.                        Triaxial Respense-Spectrum Recorders 4
: a.       Fuel Building                                                         N.A.                                   R                                                           N.A.
: b.        Resetnr Bldg. Internal Structure                                      N.A.                                   R                                                           N.A.
: c.        Safeguards Building                                                   N.A.                                   R                                                           N.A.
                               $.                        Respc.ise Spectrum Ann'inciator**                                                M                                     R                                                           SA t                                                                     .-
                                 *S:',.oint verification is not applicable.
                               **With control room indication.
1.4-3                                                                                                   Rev. O s

4 ATTACHMENT 1                   DRAFT              ,
4 BASES                                                                               5 1.4 SEISMIC INSTRUMENTATION                                                         !
   !                                                                                          l The OPERABILITY of the seismic instrumentation ensures that sufficient              i espsbility is available to promptly determine t*se magnitude of a seismic event and evaluate the respons1 of those features important to safety.
This capability is required to petrit comparison of the acasured response to that used in the design basis for the facility to detet_ine if plant shutdown is required pursuant to Appendix A of 10CFR100. The instrumentation is consistent with the recommendations of Regulatory Guide          L 1.12. "Instrumentation for Earthquakas." April 1974.                                !
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1.4-4                      Rev. 0           .

ATTACHMENT 1                    DRAFT TECHNICAL REQUIREMENT 1.5 METEOROLOGICAL INSTRUMENTATION OPERABILITY CRITERIA 1.5 The meteorological monitoring instrumentation channels shown in Table 1.5.1 shall be OPERABLE.
APPLICABILITY       At all times.
COMPENSATORY ME.iSURES:
: a. k'ith one or more required meteorological monitoring channels fraperable for more than 7 days, prepare and submit a Special
                                 'leport to the Commission pursuant to CPSES Technical Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
TESTS / INSPECTIONS 1.5 Each of the above meteorological monitoring instrumentation char.nels shall be demonstrated OPERABLE:
: a. At least once per 24 hours by performance of a CHANNEL CHECK, and
: b. At least once per 184 days by performance of a CHANNEL CALIBRATION.
l l
1.5-1                       Rev. O

ATTACHMENT 1                 DRAFT TECHNICAL REQUIREMENT 1.",
TABLE 1.5.1 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT                               LOCATION               OPERABLE
: 1. WIND SPEED                                                1 of 3
: a. X-SY-4117                   Nominal Elev. 60 m.
: b. X-SY-4118                    Nomina Elev. 0 m.
: c. X-SY-4128*                  Nominal Elev. 10 m.
: 2. WIND DIRECTION                                            1 of 3
: a. X-ZY-4115                   Nominal Elev. 60 m.
: b. X-ZY-4116                   Nominal Elev. 10 e.
: c. X-ZY-4126*                  Nominal Elev. 10 m.
: 3. AIR TEMPERATURE - a T                                     1 of 2
: a. X-TY-4119                   Nominal Elev. 60 m. and Nominal Elev. 10 m.
: b. X-TY-4120                   Nominal Elev. 60 m. and Nominal Elev. 10 m.
* Mounted on backup tower.
BASES 1.5 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation enJures that sufficient meteorological data are available for estimating potential radiation doses to che public as a result of routine or accidental release of radioactive materi'Is to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of thc public and is consittent with the recommendations of Regulatory Guide 1.23. "Onsite Meteorological Programs," September 1980.
1.5-2                     Rev. 0

O ATTACHMENT 1                  DRAFT TECHNICAL REQUIREMENT 1.6 LOOSE-PART DETECTION SYSTEM OPERABIL?TY CRITERIA 1.6 The Loose-Part Detection System shall be OPERABLE.
APPLICABILITY,3     MODES 1 and 2.
COMPENSATORY MEASUR3 :
: a. With one or more Leose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to CPSES Technical Specification 6.9.2 within the next 10 days outlining the cause of the malfuncti++ and the plans for restoring the channel (s) to OPERABLE status.
TESTS /INSPECl IONS 1.6 Each channel of the f.oose-Part Detection Systems shall be demonstrated OPERABLE by performance of t
: a. A CRANNEL CHECK 4t least once per 24 hours,
: b. An ANALOG CRANNEL OPERATIONAL TEST
* at least once per 31 days, and
: c. A CRANNEL CALIBRATION at least once per 18 months.
        *Setpoint verification is not applicable.
BASEC 1.6   LOOSE PARTS DETECTION SYSTEM The OPERABILITY of the Loose-Part Detection System ensures that sufficient capability is available to detect loose metal.''.c parts in the Reactor System and avoid or mitigate damage. to Reactor System components. The allavable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133. "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
1.6-1                     Rev. O

ATTACHMENT 1                DRAFT
     , REACTOR COOLANT SYSTEM LPERATIONAL LEAXAGE LIMITING CONDITION FOR OPERATION 3.4.6.2     Raactor Coolant System leakage shall be limited to:
: a. No PRESSURE BOUNDARY LEAYJ.GE,
: b. 1 OPM UNIDINTIFIED LEAKAGE,
: c. 1 GPM total reactor-to-secondary leakage through all steam         h generators not isolated from the Reactor Coolant System and 500 gallons per day through aay one steam generator not isolated from  y the Reactor Coolant System,                                        @
: d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System,            ,
                                                                                     >=
: e. 40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 2 20 psig, and g'
: f. 0.5 GPM leakage per nominal inch of valve size up to a maximum of 5 GPM at a Reactor Coolant Syrtem pressure of 2235 2 20* psig 7
from any Reactor Coolant System Pressure Isolation Valve.           g APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
h
: a. With any PRESSURE BGUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours and 1n COLD SHUTDOWN within the following 30 y
hours.                                                             D
: b. With any Reactor Coolant System leakage greater than any one of O
the above limits, excluding PRESSURE BOUNDARY LEAKAGE and Icakage  Q ym.
from Reactor Coolant System Pressure Isolation Valves, reduce the  q 1eakage rate to within limits within 4 hours or be in a" least     ***
HOT STANDBY vithin the next 6 hours and in COLD SHUTD^
the following, 30 hours.
vithin O g
M' ame Test pressures less than 2235 psig but greater than 150 psig are         C allowed for valves where the higher pressure vould tend to diminish      g the leakage chant.el opening. Observed leakage shall be adjusted for actual pressure to 2235 psig assuming the leakage to be directly proportional to pressure dif ferential to the one-half power.
2.1-1                    Rev. O

    ?
e ATTACHMENT 1                   DRAFT M TOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)      ,
ACTION (Continued)
: c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY vithin the next 6 hours and in COLD SHUTDOWN within the following 30 hours.           %
SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be W
within each of the above limits by:                                                ,
: a. Monitoring the Reactor Coolant System Leakage Detection System required by Specification 3.4.6.1 at least once per 12 hours; g'
g
: b. Naasurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 t 20 psig E
at least once per 18 months or following any modification.          g maintenance or operation that ef fects the seal path injection       g flow and at least once per 31 days by verifying that valves 8369 A, B, C and D aire locked in their thro'stle position. The           h provisions of Spet fication 4.0.4 are not applicable for entry into MODE 3 or 4;
: c. Performance of a Reactor Coolant System water inventory balance within 12 hours afta- echieving steady state operation
* and at least once per 72 . tire thereafter during steady state operation, D
except that no more .aan 96 hours shall elapse between any two successive invintrry balances. The provisions of Specification      Q 4.0.4 are not applicable for entry into MODE 3 or 4; and            q mee
: d. Monitoring the Reactor Head F.*ange Leakoff System at least once per 24 hours,                                                       O g
M' une
      *T,yg being changed by less than 5'F/ hour.                                    C g
t 2.1-2                      Rev. O

e ATTACHMENT 1                    DRAFT REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.2.2 Each Reactor Ceolant System Pressure Isolation Valve shall be demonstrated OPERABLE by verifying leakage to be within its limits
: a. At least once per 18 months,
: b. Prior to entering MODE 2'.vhenever the plant has been in COLD b
SHUTDOWN for 72 hours or more and if leakage testing has not been performed in the previous 9 months, enept for valves 8701A,         @
8701B, 8702A, and 8702B.
: c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and                        @
: d. Following check valve actuation due to flow through the valve and
: e. As outlined in ASME Code, Section XI, paregraph IWV-3427(b).        O The provisions of Specification 4.0.4 are not applicable for entry into        @*
HODE 3 or 4.
g a.
O W
sum.
                                                                                   'O O
                                                                                    .O.
M m..
O l
s W
l
                                                                                   .P.9 i
O l                                                                                  D l
l l
l 2.1-3                        Rev. O I

o ATTACHMENT I                                                                                 DRf,T            <
Technical Requirement 2.1 TABLE 2.1-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE 3 VALVE NUMBER                                                                                                            FUNCTION                  ,
8948 A, B, C D                                                                     Accumulator Tank Discharge                                                    f 8956 A, B                  C, D                                                     Accumulator Tank Discharge                                                    i 8905 A             B, C, D                                                          SI Hot Leg Injectton                                                          '
894.1 A, B, C, D                                                                    SI Hot Leg Injection 8818 A, B, C D                                                                      RHR Cold Leg Injection                                                        ;
8819 A, B, C D                                                                      SI Ce1d L eg Injection J701 A, B                                                                          RHR Suction Isolation 8702 A, B                                                                          RHR Suction Isolation 8841 A, B                                                                          RER Hot Leg Injection 8815                                                                               CCP Cold Leg Injection                                                         !
t 8900 A B C. D                                                                      sCP Cold Leg Injection                                                         l r
1 1
1 2.1-4                                                                                Rev. 0            l

ATTACHMENT I                  DRAFT TECHNICAL REQUIRTRENT    3. ' CONTAINMENT ISOLATION VALVES NOTE:     This Technical Requirement contains the listing of Containment Isolation V$ives, and their respective testing requirements, which are subject to CPSES Techt.ical Specification 3.6.3.
Although the Technical Specification is repeated here, care must be taken not to overlook Technical Specification requirements.
l i
l 3.1-1                       Rev. 0

ATTACHMENT 1                               DRAFT CONTAINMENT SYSTEMS 3/4.6.3     CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3d ne containment isolation valves shall be OFERABLE.
APPLICABILITY MODES 1, 2, 3, and 4.
ACTION:
      *With one or more of the containment isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration           y that is open and:
: a. Restore the inoperable valve (s) to OPERABLE status within 4 hours, or
: b. Isolate e ch affected penetration within 4 hours by use of at least one ceactivated automatic valve secured in the isolation position, or O
: c. Isolate each affected penetration within 4 hours by use of at least one closed manual valve or blind flange, or d.
m Be in at least HOT STANDBY vithin the next 6 hours and in COLD            O SHUTDOWN v1. thin the following 30 hours.
g sum
_ SURVEILLANCE REQUIR,EMENTS 4.6.3.1    The containment isolation valves shall be demonstrated operable prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, D
control or power c.ircuit by performance of a cycling test, and verification         O of isolation time.                                                                   g 9
a..
Ythe requirements of Specification 3.6.3 do not apply for those valves               O cevered by Specifications 3.7.1.1, 3.7.1.5 and 3.7.1.6.
g
* CAUTION: The inoperable isolation valve (s) may be part of a systes(s),            ame Isolating the affected penetration (s) may effect the use of the system (s).
Consider the Technical Specif $ cation' requirements oc the affected system (s)      Q sq and act accordingly.                                                                 w 3.1-2                                   Rev. 0 i

ATTACHMENT 1                      DRAFT CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2    Each containment isolation valve shall be demonstrated OPERABLE at least once pet 18 months by:
: a. Verifying that on a Phase   "A" Isolation test signal, each Phase "A"  isolation valve actuates to its isolation position;
: b. Verify that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates co its isolation position; and             Y
: c. Verify that on a Containment Ventilation Isolation test signal, each ventilation valve actuates to its isolation position.          %
4.6.3.3    The isolation time of each pwar-operated or automatic valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
O O
llr D.
O W
umn 2
0 0  .
                                                                                  ==.
O N
                                                                                  .P.9 O
D 3.1-3                          Rev. O

J:
l.
ATTAC* DENT 1        . DRAFT TECHNICAL REQUIRl! MENT 3.1 TABLE 3.1.1 C0NTAINMENT ISOLATION VALVES MAXIMLP*
ISOLATION      - TYPF.
FSAR TABLE                                                       TIME        LEAK TEST        ;
VALVE NO.       REFERENCE NO.*                              LINE OR SERVICE        (Seconds) REQUIREMENTS
: 1. Phase  "A" Iso 16 lon Valves                                              '.  .'
1HV-2154                    20                           Feedwater Sample              5       Note 1 (FW to Sta con #1) 1HV-2155                    22                          Feedwater Sample              5        Nota 1            ,
                                                                                       -(FW to Sta Cen #2) r 1HV-2399                     27                          Blowdown From Steam           5        Note 1 Cenerator #3 1HV-2398                     28                          Blowdown From Steam           5        Note 1 Generator #2 INV-2397                    29                           Blowdown From Steam           5        Note 1            ;
Cenerator #1                                             l
,                                                                                                                                                i
)                              1HV-2400                    30                           Blowdown From Steam           5        Note 1            i
:                                                                                       Generstor #4                                             ,
1
(                              1-8152                      32                           Letdown Line to              10       C                  !
Letdown Heat Exchanger                                   I 1-8160                      32                           Letdown Line to              10       C
* Letdown Heat Exchanger                                    ;
W 1-8890A                     35                           RHR to Cold Leg Loops        15       Note 2
                                                                                        #1 & #2 Test Line                                        [
t 1-88908                     36                          RHR to Cold Leg Loops         15       Note 2             :
f3 & #4 Test Line                                         '
i 1-8047                     41                           Reactor Makeup Yater          10       C to Pressure Relief                                        r Tank & RC Pump Stand                                      :
Pipe
[
1-8843                     42                           SI to RC System Cold          10       Note 2             ;
Leg Loops fl. #2. f3. f4                                  ,
Test Line                                                 j i
t k
3.1-4          Rev. 0 i

I ATTACHMENT 1                DRAFT TECHNICAL REQUIREMENT 3.1                             <
TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION       TYPE    (
FSAR TABLE                                 TIME        LEAK TEST VALVE NO. REFERENCE NO.
* LINE OR SERVICE          (Seconds) REQUIREMENTS
: 1.                     Phase   "A" Isolation Valves 1-8881              43       SI to RC System Hot Leg      10       Note 2 Loops #2 & #3 Test Line 1-8824              44       SI to RC System Hot Leg      10       Note 2 3                                                           Loops #1 & #4 Test Line 1-8823               45       SI to RC System Cold Leg     10       Note 2 Loops #1, f2. f3 & #4 Test Line 1-8100               51      Seal Water Return             10       C and Excess Letdown 1-8112               51      Seal Water Return             10       C and Excecs Letdown
;                              1-7136               52      RCDT Heat Exchanger           10       C
;                                                           to Waste Hold Up Tank LCV-1003             52      RCDT !! eat Exchanger         10       C to Waste Hold Up Tank 1HV-5365             60      Demineralized Water Supply     5       C 1HV-5366             60      Demineralized Water Supply     5       C 1HV-5157             61      Containment Sump Pump          5       C Discharge 1HV-5158             61      Containment Stimp Pump         5       C Discharge 1HV-3487             62      Instrument Air to              5       C Containment 1-8825               63      RHR to Hot Leg Loops          15      Note 2 f2 & f3 Test Line 1HV-2405             73      Sample from Steam              5      Note 1 Cenerator #1 1HV-4170             74      RC Sample From Hot Legs        5      C 3.1-5                    Rev. O
: c.                __                     _

0 c.
ATTAC10ENT 1                 DRAFT TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMLH ISOLATIDW        TYPE FSAR TABLE                                  TIME         LEAK TEST VALVE NO. REFERENCit NO.*   LINE OR SERVICE           (Seconds) REQUIREMENTS
: 1. Phase "A" Isolation Valves (Continued) 1HV-4168           74       RC Sample From Ho.t Les #1      5      C IHV-4169           74       RC Sample From Hot Les f4       5       C INV-2406          76        Sample from Steam               5      Note 1 Generator #2 1HV-4167          77        Pressuriser Liquid             5       C Space Sample i
1HV-4166          77        Pressuriser Liqvid             5       C Space Sample 1HV-4176          78        Pressuriser Steam              5       C Space Sample JHV-4165          78        Pressuriser Steam              5       C Space Sample I
1HV-2407          ,9        Sample Trom Steam              5       Note 1 Cenerator #3 i
i           1HV-4175          80        Accumulators                   5       C 1HV-4171          80        Sample From                    5       C Accumulator il 1HV-4172          80        Sample From                    5       C Accumulator #2
)          1HV-4173           30        Sample From                    5       C l                                       Accumulator #3 JHV-4174           80       Sample From                     5       C Accumulator #4 j          1HV-7311          81        RC PASS Sample                  5       C Discharge to RCDT l          IHV-7312          81        RC PASS Sample                  5       C l                                      Discharge to RCDT f          1HV-2408          82        Sample from Steam               5      Note 1 i                                      Cenerator f4 i
I 3.1-6                     Rev. O

     '/'
ATTACHMENT 1                DRAFT TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION       TYPE FSAR TABLE                                                                                                                                                          TIME        LEAK TEST VALVE NO. REFERENCE No.*                                                                                                                             LINE OR SERVICE          (Seconds) REQUIREMENTS
: 1.                 Phase  "A" Isolation Valves (Continued)
  ;:                                        1-8871                                                83                                                                                              Accumulator Test and Fill    10       C 1-8888                                                83                                                                                              Accumulator Test and Fill    10       C 1-8964                                               83                                                                                               Accumulator Test and Fill    10       C 1HV-5556                                             84                                                                                               Containment Air PASS          5       C
                                                                                                                                                          .                                       Return 1
1HV-5557                                             84                                                                                               Containment Air PASS          5       C Return 1HV-5544                                             94                                                                                               Radiation Monitoring          5       C Sample 1HV-5545                                             94                                                                                               Radiation Monitoring          5       C Sample 1HV-5558                                             97                                                                                               Containment Air PASS Inlet                         5       C 1HV-5559                                            97                                                                                                Containment Air PASS Inlet                         5       C 1HV-5560                                   100                                                                                                        Containment Air PASS Inlet                         5       C 1HV-5561                                   100                                                                                                        Containment Air PASS Inlet                         5       C 1HV-5546                                   102                                                                                                        Radiation Monitoring          5       C Sample Return e
1HV-5547                                  102                                                                                                         Radiation Monitoring          5       C Sample Return 1-8880                                    104                                                                                                         Na Supply to Accumulators    10      C 1-7126                                    105                                                                                                          H Supply to RC Drain         10      C Tank 3.1-7                    Rev. O

C f
ATTACHMENT 1                                                                                                  DRAFT                                    '
TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)                                                                                                                                         !
CONTAINMENT ISOLATION VALVES MAXIMUM                                                                            i ISOLATION                                           TYPE FSAR TABLE                                                                                TIME                                            LEAK TF.ST                        i VALVE NO. RFFERENCE NO.
* LINE OR SERVICE                                                        (Seconds) REQUIREMENTS                                                              i
: 1. Phase   "A" Isolation Valves (Continued)
(
1-7150             105        H Supply to RC Drain                                                        10                                          C                                  I Tank                                                                                                                                                        l 1HV-4710            111       CC Supply to Excess                                                                  5                                  Nota 1                              l Letdown & RC Drain                                                                                                                                          '
Tank Heat Exchanger                                                                                                                                         !
1HV-4711            112       CC Return From Excess                                                               5                                  Note 1                              [
Letdown & RC Drain                                                                                                                                         ;
Tank Heat Exchanger                                                                                                                                         i 1HV-3486           113         SLrvice Air to                                                                     5                                    C Containment 1HV-4725           114        Containment CCY Drain                                                               5                                   C j-                                        Tank Pumps Discharge                                                                                                                                        L i           1HV-4726           114        Containmeat CCW Drain                                                               5                                   C                                   !
Tank Fumps Discharge                                                                                                                                        !
l-8027             116        Nitrogen Supply to PRT                                                      10                                          C 1-8026             116        Nitrogen Supply to PRT                                                      10                                          C INV-6084           120        Chilled Water Supply                                                        10                                          C                                   !
to Containment Coolers                                                                                                                                      i
{
1HV-6082           121        Chilled Water Return                                                        10                                          C                                   !
From Containment Coclers                                                                                                                                    (
i                                                                                                                                                                                                     -
1HV-6083           121        Chilled Water Return                                                        10                                          C                                  I From Containment Coolers                                                                                                                                   !
l'
)           1HV-4075B          124        Fire Protection dy.66c                                                      10                                          C
;                                         Isolation                                                                                                                                                  i t
     .      1HV-4075C         124         Fire Protection System                                                      10                                          C                                   L
:                                         Imolation r
l I
t 3.1-8                                                                                               Rev. O                                          i i

                      .O                               .
s
                    .                                                                                                                                                                                                                 l ATTACHMENT 1 ,
DRAFT                             i TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES 4
MAXIMUM ISOLATION        TYPE FSAR TABLE                                                                                                            TIME         LEAK TEST VALVE NO. REFERENCE NO.*                                   LINE OR SERVICE                                                              (Secondel REQUIREMENTS
: 2.                        Phase "B" Isolation Valves                                         -
lHV-4708                       117               CC Return From RCP's                                                                        10       C Motors INV-4701                       117               CC Return From RCP's                                                                        10       C Motars INV-4700                       118              CC Supply to RCP's                                                                           10       C Motors iKV-4709                        119              CC Return From RCP's                                                                         10       C Thermal Barrier 1HV-4696                       119              CC Return From RCP's                                                                         10        C Thermal Barrier
: 3.                      Containment Ventilation Isolation Valves I
1HV-5542                         58            Hydrogen Purge Supply                                                                         NA       C 1HV-5543                         38            Hydrogen Purge Supply                                                                         NA       C INV-5563                         58            Hydrogen Purge Supply                                                                         NA       C 1HV-5540                         59            Nydrogen Purge Exhaust                                                                        NA       C
;                                                 1NV-5541                         59            Hydrogen Purge Exhaust                                                                        NA       C i                                                 1HV-5562                         59            Hydrogen Purge Exhaust                                                                        NA       C i                                                lHV-5536                        109             Co tainment Purge Air                                                                        NA        C Supply 1HV-5537                        109             Containment Purge Air                                                                        NA        C Supply IHV-3538                        110             Containment Purge Air                                                                        NA        C Exhaust IHV-5539                        110             Containment Purge Air                                                                        NA       C Exhau1t 3.1-9                                                                       Rev. O

ATTACHMENT 1                DRAFT TTCHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION       TYPE FSAR TABLE                                TIME        LEAK TEST VALVE NO. REFERENCE NO.*     1.INE OR SERVICE        (Seconde) REQUIREHENTS
: 3.        Containment Ventilation Isolation Valvis (Continued) 1HV-5548        122         containment Pressure          3      C Relief 1NV-5549        122         Containment Pressure          3      C Relief
: 4.         Manual Valves 1MS-711          4a         TDAFW Pump Warm-up Valve   N.A.      Note 1. 11 IMS-390          5a         Na Supply to Steam         N.A.      Note 1 Generator il 1MS-387          9a        Na Supply to Steam          N.A.      Note 1 Generator #2 1MS-384          13a        Na Supply to Steam          N.A.      Note 1 Generator #3 1MS-712          17a        TDAfW Pump Warm-up Valve    N.A. Note 1. 11 1MS-393          18a        Na Supply to Steam          N.A. Note 1 Generator f4 1TW-106          20b        Na Tupply to Steam          N.A. Note 1 Centrator #1 1FW-104          22b        Na Supply to Steam          N.A. Note 1 Generator #2 1rW-110           24        Secondary Saepling          N.A. Note 1 1TW-102         24b         Na Supply to Steta          N.A. Note 1 Generator #3 IFW-119           26        Secondary Sampling          N.A. Note 1 IFW-108         26b         Na Supply to Steam          N.A. Note 1 Cenerator #4 1-7135            52        RCDT Heat Exchanger to      N.A. C Waste Holdup Tank 3.1-10                   Rev. 0

3 !4 ATTACHMENT 1'                                                                                           DRAFT
:                                                                                                         TECHNICAL REQUIREMENT 3.1-TABLE 3.1.1 (Contint.ed)                                                                                                                          [
l CONTAINMENT ISOLATION VALVES, MAXIMUM                L ISOLATION       TYP..   !
FSAR TABLE                                                                                                                             TIME        LEAK TEST !
                                                                                 ,V,,ALVE NO. REFERENCE NO.*    LINE OR SERVICE                                                                                                      (Seconds) REQUIREMENTS  f a                                                                                                                                                                                                                                                            i
: 4.                                     Manual Valves (Cont.inued)                                                                                                                                                  [
,                                                                                 ISFe011           56         Refueling Water                                                                                                         N.A.      C           I Purification to                                                                                                                               I Refueling Cavity ISF-012           56         Refueling Water                                                                                                         N.A.      C           l Purification to
,                                                                                                              Refueling Caving                                                                                                                              l l
ISF-021           67        Refueling Cavi,; to                                                                                                      N.A.      C Refueling Water                                                                                                                                "
Purification Pump                                                                                                                              j ISF-022           67        Refueling Cavity to                                                                                                      N.A.      C           l Refueling Water                                                                                                                                i Purification Pump                                                                                                                              ,
ISF-053            71        Refueling Cavity                                                                                                         N.A.      C           l Skimmer Pump Discharge                                                                                                                         i
.                                                                                ISF-054            71        Refueling Cavit;-                                                                                                        N.A.      C           t Skimmer Pump Dist.fiarse                                                                                                                       ;
: j.                                                                               lHV-2333B           2        MSIV Bypass from Ste m                                                                                                   N.A.      Note 1. 6   !
t Generator il                                                                                                                                   ;
i lHV-2334B           7        MSIV Bypass from Steam                                                                                                   N.A.      Note 1, 6   i Generator #2 1HV-2335B          11        MSIV Bypass from Stea.m                                                                                                  N.A. Note 1. 6
,                                                                                                             Generator #3 1HV-2336B          15        MSIV Bypass from Steam                                                                                                   N.A. Note, 1, 6   t Generator f4
: 5.                                          Power-Operated Isolation Vaav.s 1HV-2452-1           4        Main Steam to Aux. FPt                                                                                                   N.A. Note 1       !
From Steam Line il                                                                                                                             !
t l                                                                               IPV-2325             5        Atmospheric Relief                                                                                                       N.A. Note 1       !
i                                                                                                             Steam Generator il                                                                                                                             f s
l                                                                                                                                                                                                                                                             t i                                                                                                                                             3.1-11                                                                                        Rev. 0 l\

ATTACHMENT 1                            DRAFT TECHNICAL REQUIR2 MENT 3.1 TABLE 3.1.1 (Continued)
CONTAINNENT ISOLATION VALVES MAXIMUM                 i ISOLATION                    TYPE    !
FSAR TABLE                                                      TIME       LEAK TEST ;
VALVE NO. REFERENCE NO.*              LINE OR SERVICE       (Seconds) REQUIREMENTS
: 5. Power-Ope. rated Isolation Valves (Continued)                                                       i i
IPV-2326            9                 Atmospheric K lief                      N.A.      Note 1     h Steam Generator #2                                           ;
i 1PV-2327           13                 Atmospheric Relief                      N.A. Note 1      !
Steam Generator #3                                           ;
1HV-2452-2         17                 Main Steam to Aux. FPT                  N.A. Note 1 From Steam Line #4                                           [
IPV-2328           18                 Atmospheric Relief                      N.A. Note 1      f Steam Ger arator #4                                          l 1HV-2491A          20a                 Auxiliary Feedwater to                  N.A. Note 1      l Steam Generator #1                                           F 1HY-2491B          20a                 Auxiliary Feedwater to                  N.A. Note 1      -
l                                                               Steam Generator il
                  .      IhV-2492A          '?a                Auxiliary Feedvater to                   N.A. Note 1 Steam Generator #2 3 ,-
1HV-2492B          22s                Auxilia:y Feedwater to                   N.A. Note 1 Steam Generator #2
'l
:                        1HV-2493A          24a                Auxiliary Feedwater to                   N.A. Note 1
;                                                              Steam Generator #3 l
l                        1HV-24938         24a                 Auxiliary Feedwater to                   N.A. Note 1 Steam Generator #2 1HV-2494A         26a                 Auxiliary Feedwater to                   N.A. Note 1 Steam Generator f4 i
f                        1HV-21.'94 E      26a                 Auxiliary Feedwater to                   N.A. Note 1 l                                                              Steam Generator #4
;                        1-8701B           33                  RHR From Hot Leg Loop #4                 N.A. Note 5 l                        1-8701A           34                  RHR From Hot Leg Loop fl                 N.A. Note 5 i                        1-8809A           35                  RHR to Cold Leg Loops                    N.A. Note 4 il and #2 3.1-12                                Rev. 0 4
L

I e
ATTACHMENT 1                 DRAFT TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES i,
MAXIMUM                  r ISOLATION       TYPE FSAR TABLE                                  TIME        LEAK TEST VALVE NO. REFERENCE NO.*    LINE OR SERVICE           (Seconds) REQUIREMENTS
: 5. Power-Operated Isolation Valves (Continued) 1-8809B          36        RHR to Cold Leg Loops        N.A.      Note 4       :
                                          #3 and #4                                            '
1-8801A          42        High Head Safety Injection   N.A.      Note 7       i to Cold Les Loops #1, #2,
 ,                                        #3, and f4                                           ,
l              1-8801B         42         High Head Safety Injection   N.A.      Note 7       !'
to Cold Leg Loops #1 !2,                           ,
                                          #3, and #4
'                                                                                            1 1-8802A 43         SI Injection to Hot Leg      N.A.      Note 8 j                                         Loops #2 and #3 1-8802B         44         SI Injection to Hot Leg      N.A.      Note 8 Loops #1 and #4                                    .
1-8835           45         SI Injection to Cold Leg     N.A.      Note 4      ft Loops #1, #2, 81, and #4
!             l-8351A          47         Seal Injection to RC         N.A.      C i
Pump (Loop #1) i             1-8351B          48         Seal Injection to RC         N.A.      C            i Pump (Loop #2)                                      '
,             1-8351C          49         Seal Injection to RC         N.A.      C j                                        Pump (Loop 3)                                        [
l 1-8351D          50        Seal Injection to RC          N.A.      C            !
Pump (Loop #4)                                       j lHV-4777         54        Containment Spray to          N.A. Note 3        I Spray Header (Tr. B)                                 [
i IHV-4776         55        Containment Spray to          N.A.     ..ote 3       [
Spray Header (Tr. A) 1 e840           63        RHR to Hot Leg Loops          N.A. Note 8       I
                                         #2 and #3 f
3.1-13                     Rev. 0           l l
(

e                  .
                                                                                                                  ?
r      ATTACHMENT 1                DRAFT           ,
TECHNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)                               i C0ATAINMENT ISOLATION VALVES f
MAXIMUM ISOLATION       TYPE    [
FSAR TABLE                                 TIME        LEAK TEST !
VALVE NO. REFERENCE NO.*      LINE OR SERVICE        (Seconds) REQUIREMENTS
: 5. Power-Operated Isolation Valves (Continued) 1-8811A        125          Contair:sent Recire.       N.A.      Note 1, 10  ;
Sump to RHR Pumps                                !
(Train A)                                       j 1-88118        126          Containment Recire.        N.A.      Note 1. 10  !
Susp to RER Pumps (Train B) 1HV-4782       127          Containment Recire.        N.A.      Note 1. 10 to Spray Pumps (Train A)
)                                    1HV-4783       128         Containment Recire.         N.A.      Note 1. 10 4                                                                to Spray Pumps y                                                                (Train B) l
: 6. Check Valves i
i                                    1-8818A         35         RHR to Cold Leg Loop fl     N.A.      Note 2 1 9818B         35         RHR to Cold Leg Loop f2     N.A.      Note 2
;                                    1-t818C         36         RHR to Cold Leg Loop f3     N.A.      Note 2 1-8818D         36         RER to Cold Leg Loop #4     N.A.      Note 2 4
;                                   1-8046           41         Reactor Makeup Water to     N.A.      C j                                                              Pressurizer Relief Tank i                                                              and RC Pump Stand Pipe l                                   1-8815           42        High Head Safety Injection   N.A.      Note 2 i
to Cold Leg Loops #1, f2 j                                                              #3, and #4 l                                   1SI-8905A        44        SI co RC System Hot Les      N.A. Note 2 Loop fl ISI-8905B        43        SI to RC System Hot leg      N.A. Note 2 Loop #2 ISI-8905C       43         SI to RC System Hot '.eg     N.A. Note 2 Loop #3 3.1-14                   Rev. O

v e.
ATTACHMENT 1               DRAFT TECHNICAL REQUIRDCNT 3.1 TABLE 3.1.1 (continued)
CONTAINMENT ISOLATION VALVES                                       :
MAXIMUM ISOLATION           TYPE FSAR TABLE                                           TIME            LEAK TEST VALVE NO. REFERENCE NO.*                 LINE OR SERVICE       (Seconds) REQUIREMENTS      '
: 6. Check Valves (Continued)                                                                    f l
1SI-8905D        44                     SI to RC System Hot Leg   N.A.          !!ote 2     .
Loop #4                                             !
ISI-8819A        45                     SI to RC System Cold      N.A.          Note 2      E Leg Loop #1                                          ,
t 1SI-8819B        45                     SI to RC System Cold      N.A.          Nota 2 Les Loop #2 1SI-8819C       45                      SI to RC System Cold      N.A.          Note 2 j                                                      Leg Loop #3 l               1SI-8819D        45                    SI to RC System Cold       N.A.          Note 2      7
;                                                      Leg Loop #4 1-8381          46                     Charging Line to           N.A.          C           i Regenerative Heat                                    I l
Exchanger                                            !
ICS-8368A       47                     Seal Injection to RC       N.A.          C
;                                                      Puer G.oo? f1)                                       [
1CS-8368B       48                     t'eal Injection to RC      N.A.          C.
Pump (Loop #2)                                       !
s 1
1CS-8368C        49                     Seal Injection to RC       N.A.          C           '
Pump (Loop #3) 1CS-8368D        50                     Seal Injection so RC       N.A.         C Pump (Loop #4)                                       f L
1C5-8180         51                     Seal Water Return and      N.A.         C            L Excess Letdown                                       l t
ICT-145          54                    Centainment Spray te        N.A.         Note 3       !
Spray Header (Tr. B)                                 j
;              ICT-142          55                    Containment spray to        N.A.         Note 3
)                                                     Spray Header (Tr. A) l              ICT-030          62                    Instrument Air to           N.A.         C Containment i
1 i
3.1-15                    Rev. O I

ATTACHMENT 1                                                                                         DRAFT TECHNICAL REQUIREMENT 3.1 TAELE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM IS( LATION       TYPE FFAR TABLE                                                                                                           TIME         LEAK TEST VALVE NO. REFERENCE N0 i*       LINE OR SERVICE                                                                                 (Seconds) REQUIREMENTS 1-8841A          63         RHR to Hot Leg Loop #2                                                                                N.A.       Note 2 1-8841B          63         RHR to Hot Leg Loop #3                                                                                N.A.       Note 2 1SI-8968        104         Na Supply to Accumulators                                                                             N.A.       C 1CA-016         113         Service Air to                                                                                        N.A.       C Containment ICC-629         117         CC Return From RCP's                                                                                  N.A.       C Motors 10C-713         118         CC Supply to RCP's Motors                                                                             N.A.       C 10C-831         119         CC Return From RCP's                                                                                  N.A.       C Thermal Barrier ICH-024         120         Chilled Water Supply to                                                                               N.A.       C Containment Coolers
: 7. Steam Line Isolation Signal 1NV-2333A          1        MSIV #1                                                                                                  5       Note 1.9.12 1HV-2409          3         Drain Frau Main Steam                                                                                    5       Note 1 Line il 1HV-2334A         6        MSIV #2                                                                                                   5       Note 1.9.12 1HV-2410          8        Drain From Main Steam                                                                                     5       Note 1 Line #2 1HV-2335A        10         MSIV #3                                                                                                  5      Note 1.9.12 1HV-2411         12        Drain from Main Steam                                                                                     5      Note 1 Line #3 1HV-2336A        14        MSIV #4                                                                                                   5      Note 1.9.12 1HV-2412         16        Drain From Main Steam                                                                                     5      Note 1 Line #4 3.1-16                                                                                             Rev. O

ATTACHMENT 1                                   DRAFT                                 I J
TECHNICAL REQUIREMENT 3.1                                                                            j TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALVES                                                                           ,
MAXIMUM                                      ;
ISOLATION                      TYPE           !
FSAR TABLE                                                           TIME            LEAK TEST                   !
VALVE NO. REFERENCE No.*      LINE OR SERVICE                                  (Seconds) REQUIREMENTS
: 8. Feedwater Lino Isolation Signal A
1HV-2134          19         Feedwater Isolstion                                    5         Note 1, 12
* Steam Generator il                                                                              i i
1FV-2193          20e        Feedwater Preheat Bypass                               5         Note 1, 12 Line S.G. #1 1HV-2185          20d        Feedvater Isolation                                    5         Note 1, 12                     f q                                        Bypass Line S.C. il 1HV-2135           21         Feedwater Isolation                                    5        Note 1. 12                      !
Steam Generator #2                                                                               !
}
ITV-2194           22c       Feedwater Preheat Bypass                                5        Note 1, 11 2
Line S.C. #2                                                                                     L 1HV-2186          22d        Feedvater Isolation                                     5        Note 1, 12                      i Bypass Line          S.C. #2
{
1HV-2136          23         Feedwater Isolation                                     5        Note 1. 12                      !
Steam Generator #3                                                                               !
j          1FV-2195          24c        Feedvater Preheat Bypass                                5        Note 1, 12                      >
l                                       Line S.C. f3
!          1HV-2187          24d        Feedwater Isolation                                     5        Note 1, 12                       [
!                                       Bypass Line S.C. f3                                                                               i i
i 1HV-2137          25         Feedwater Isolation                                     5        Note 1. 12                      !
j                                       Steam Generator #4                                                                               j i                                                                                                                                         i i          t r'V-2196        26d        Feedvater Preheat Bypass                                5        Note 1. 12
)
Line S.G. f4                                                                                      !
r 1HV-2188          26e        Feedvater Isolation                                     5       Note 1. 12 Bypass Line S.C. #4 i      9. Safety Injection Actuation Isolation                                                                                           i i
'                                                                                                                                         I 1-8105            46        Charging Line to                                        10       C                                j
]                                      Regenerative Heat                                                                                  t i                                      Exchanger                                                                                         j i
i                                                                                                                                         !
j                                                     3.1-17                                       Rev. O                                 !
l                          -           _ - . - _ _ -.                                            -     - - - - - - -

g                                                       --_    _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _                       _ _ _ . _ _ _
         ,-+                                                                                                                                               >
I ATTACHMENT 1                                                               DRAFT                          i TECHNICAL REQUIREMENT 3.1 i
TABLE 3.1.1 (Continued) i CONTAINMENT ISOLATION VALVES MAXIMLH                             I ISOLATION            TYPE                  !
FSAR TABLE                                                                               TIME       LEAK TEST               ,
VALVE NO. REFERENCE NO.*    LINE OR SERVICE                                                   (Seconde) REQUIREMENTS                    ;
: 10. Relief Valves                                                                                                                             !
b                                                                                                                                                          I 1-8708B          33         RHR From Hot leg Loop f4                                                  N.A.      Note 5 l
l-8708A          34         RHR From Hot Les Loop fl                                                  N.A.      Note 5 f
1MS-021          5b        Main Steam Safety Valve                                                    N.A.      Note 1, 12
;                                             S.G. il 1                                                                                                                                                          1 1MS-022          $b        Main Steam Safety Valve                                                    N.A.      Note 1, 12               !
S.C. il                                                                                                      !
IMS-023          Sb        Main Steam Safety Valve                                                    N.A.      Note 1, 12 S.G. fl IMS-024          Sb        Main Steam Safety Valve                                                    N.A.      Note 1. 12               {
S.G. #1 j                IMS-025           Sb        Main Steam Safety Valve                                                    N.A.      Note 1, 12               '
 !                                           S.C. #1 IMS-058           9b        Main Steam Safety Valve                                                    N.A.      Note 1, 12               ,
S.C. f2                                                                                                       ;
;                IMS-059           9b        Main Steam Safety Valve                                                    N.A.      Note 1. 12 i                                           S.G. f2                                                                                                       >
i                IMS-060           9b        Main Steam Safety Valve                                                    N.A. Note 1, 12                !
 ;                                           S.C. f2                                                                                                       -
r IMS-061           9h        Main Steam Safety Valve                                                    N.A. Note 1,12                 i S.G. f2                                                                                                       l
 ,               IMS-062          9b         Main Steam Safety Valvo                                                   N.A.      Note 1, 12 S.G. #2                                                                                                       {
IMS-093           13b       Main Steam Safety Valva                                                   N.A.      Note 1, 12 S.C. f3                                                                                                       (
j              IMS-094           13b       Main Steam Safety Valve                                                   N.A.      Note 1. 12                f
 ;                                           S.C. f3                                                                                                       i 1MS-095          13b        Main Steam Safety Valve                                                   N.A.      Note 1, 12                [
l                                           S.G. f3 I
t i
3.1-18                                                                   Rev. O                        !
l 1

I l
ATTACHMENT 1                  DRAFT
        "                                                                                                                                  i f
TECKNICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)                                !
CONTAINMENT ISOLATION VALVES C
MAXIMUM ISOLATION        TYPE FSAR TABLE                                 TIM 2        LEAK TEST VALVE NO.             REFERENCE NO.*                    LINE OR SERVICE          (Seconds) REQUIREMENTS L
: 10. Relief Valves (Continued)                                    h                                           I i
1MS-096                                     13b       Main Steam Safety Valve     N.A.       Note 1. 12 S.G. f3                                            i IMS-097                                     13b      Main Steam Safety Valve      N.A.       Note 1. 12  l S.G. f3                                            ,
IMS-129                                     18b      Main Steam Safety Valve      N.A.       Note 1. 12  .
S.G. f4                                            l r
i 1MS-130                                     18b      Main Steam Safety Valve      N.A.       Note 1. 12 S.G. #4                                            l 1MS-131                                     18b      Main Steam Safety Valve      N.A.       Note 1. 12  ;
S.C. f4                                             '
1MS-132                                     18b      Main Steam Safety Valve      N.A.       Note 1. 12 S.G. f4 1MS-133                                     18b      Main Steam Safety Valve      N.A.       Note 1. 12 S.C. f4 1RC-036                                    41        RMUV To PRT & RCP            N.A.       C Standpipe IWP-7176                                    52        RCDT HX to Waste             N.A.       C Holdup Tank 1DD-430                                     60        Dominera11:ed Water Supply   N.A.      C IVD-907                                     61        Containment Sump Pump        N.A.      C Discharge 1PS-193                                     80        Sample from Accumulators     N.A.      C 1CC-1067                                   114        Containment CCW Drain        N.A.      C Tank Pump Discharge ICH-271                                    120        Chilled Vater Supply to      N.A.      C Containment Coolers ICH-272                                    121        Chilled Water Supply         N.A.      C from Containment Coolers 3.1-19                      Rev. O

ATTACHMENT 1                   DRAFT TABLE 3.1.1 (Continued)
TABLE NOTATIONS
* Identification code for containment penetratien and associated isolation valves in FSAR Tables 6.2.4-1. 6.2.4-3. and 6.2.4-3.
Note 1:      These are closed systems which meet the requirements of VUREG-0800 Section 6.2.4. II.6 paragraph o. These valves are trerefore not required to be leak tested.
Note 2:      These valves inside containment are part of closed systfas outside containment which are in service post accident at a presimre in excess of containment design pressure and satisfy singit failure criterion. These valves are therefore not required to be leak tested.
Note 3:      These are closed systems outside containment which are in service post accident and have a water filled loop seal on the containment side of the valves for a period greater than 30 days following the accident. These valves are therefore leak rate tested with water of a pressure of P,.
Note 4:      These ESF valves are normally open and remain open during post-accident conditions. Post-accident they are continually pressurized in excess of containment pres.nure from an ESF source which meets the single failure criterion. These valvas are therefore not required to be leak tested.
Note 5:     An effective fluid seal on these penetrations is provided by the suction sources to the residual heat removal pumps during and following an accident. In addition, these containment isolation valves are non-automatic, are not required to operate              ,
post-accident and are located inside containment. These valves     !
are therefore not required to be tested.                           I Note 6:     All four MSIV bypass valves are locked closed in Mode 1. During Mode 2. 3. and 4 one MSIV bypass valve may be opened provided the other three MSIV bypass valves are locked closed and their         i associated MSIVs are closed.
Note 7:     These are parallel ESF valves that are normally closed, but are designed to open during post-accident conditions. Failure of one   1 valve to open vill not prevent system pressurization on both sides of both valves in excess of containment pressure. These      ,
valves are sherefore not req:iire6 to be leak tested.              I Note 8:     These valves located outside con ainment are normally closed and see a pressure in excess of containment pressure in post-accident  ,'
conditions. A valve stem leakage check vill be performed on a quarterly basis to ensure no significant stem leakage would occur in post-accident conditions.
i Note 9:     These valves require steam to be tested and are thus not required  [
to be tested until the plant is in MODE 3.
I 3.1-20                       Rev. 0      '

ATTACHMENT 1                   DRAFT TABIE 3.1.1 (Continued)
TABLE NOTATIONS Note 10   These valves vill have water against them during post-accident conditions to praclude any release of containment atuosphere to the environment.
Note 11: These valves are normally locked closed and are open only to warm up the steam supply lines prior to normal surveillance testing.
Note 12   These valves are included for table completeness, the requirements of Specification 3.6.3 do not apply. Instead, the requirements of Specification 3.7.1.1, 3.7.1.5 and 3.7.1.6 apply for main steam safety valves, mainsteam isolation valves, and feedvater isolacion valves, respectively.
BASES 3.1       CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere vill be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment aad is consistent with the requirements of General Design Criteria 54 through 57 of 10CFR50 Appendix A.
Containment isolation within the time limits specified for those isolation valves designed to close automatically enseres that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
l f
f 3.1-21                       Rev. O

l-
: l.                                                                                                                                       >
ATTACHMENT 1                                                         DRAFT TECHNICAL REQUIREMENT 4.i $NURBER INSERVICE INSPECTION PROGRAM NOTE:     This Technical Requirement contains the augmented insetvice inspection program for snubbers. Although the CPSES Technical Specification is repeated here, in part, care must be taken not l               to overlook Technical Specification requirements.
l l
1 l
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t 4.1-1                                                             Rev. O i

ATTACHMENT 1                      DRAFT PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9      All snubbers shall be OPERABLE. The only snubbers excluded from the tsquirements are those installed on nonsafety-related systems and then only if their failure, or failure of the system on which they are installed would have no adverse effect on any safety-related system.
APPLICABILITY:      MODES 1, 2, 3, and 4.
on systems required OPERABLE in those MODES.
MODES 5 and 6 for snubbers located                                    %
ACTION:
With one or more snubbers inoperasle, within 72 hours replace or restore the inoperable snubber (s) to OPERJ.BLE status and perform an engineering evaluation in accordance with the approved augnented inservice inspection program, on the attached component or declare the attached system (s) inoperable and follow the approprfate ACTION statement for that system (s).                                        4  <
SURVEILLANCE REQUIREMENTS O
Q 4.7.9       Each anubber sball be demonstrated OPERABLE by performanes of                                          E the requirements of the approved augmented inservice inspection program.                                           g O
W
                                                                                                                       ~
13 O
O N
                                                                                                                      ==.
W n
sm.
0 3
4.1-2                       Rev. O

O e
ATTAC10ENT 1                            DRAFT Technical Requirement 4.1 SNUBBER INSERVICE INSPECTION PROGRAM (1.ATER) a 4.1-3                 Rev. O

O ATTACHMENT 1              DRMT TECHNICAL REQUIREMENT 4.2 SEALED SOURCE CONTAMINATION OPERABILITY CRITERIA 4.2         Each sealed source containing radioactive matsrial either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be fres of greater than or equal to 0.005 microcurie of removable contamination.
APPLICABILITY:      At all times.
COMPENSATORY MEASURES:
i With a sealed source having removabis .ontamination in excess of the above limits, immediately withdraw the sealed source from use and either:
: 1. Decontaminate and repair the sealed source, or
: 2. Dispose of the sealed source in accordance with Commission Regulations.                                                          l TESTS / INSPECTIONS 4.2.1       Test Requirements - Each sealed source shall be tested for leakage and/or contamination by
: a. The licensee, or
: b. Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
4.2.2       Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.                          l
: a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials
: 1)     With a half-life greater than 30 days (excluding        -
Hydrogen 3), and                                        i
: 2)      In any form other than gas, i
l 4.2-1                 Rev. O    !
l

O ATTACHMENT 1                                                                                                           DRAFT TECHNICAL REQUIREMENT 4.2 SURVEII.I.ANCE REQUIREMENTS (Continued)
: b. Stored sources not in use - Each sealed source and fission detector shall be ested prior to use or transfer to another
* licensee unless tested within the previous 6 months. Sealed                                                                                                    ;
sources and fiJsion detectors transferred without a certificate indicating the last test date shall be tested prict to being                                                                                                   [
placed into use: and
: c. 3tartup sources and fission detectors - Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjectes to core flux and following repair or maintenance to the source.
4.2.3                         Repotta - A report shall be prepared and submitted to the Commission on an annual basis it sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.
i I
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{
BASES r
4.2                        SEALLD TOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak                                                                                                                          (
testing, including alpha emitters, in based on 10Cra70.39(c) limits for plutonium. This limitation vill ensure that leakage from Byproduct.                                                                                                                          1 Source, and Special Nuclear Material sources vill not exceed allowabla intake values.                                                                                                                                                                                i l
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage                                                                                                                      ,
to a source in that group. Those sources which are frequently handled are                                                                                                                      !'
required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded techanism (i.e., sealed                                                                                                                         '
sources within radiation monitoring or boron reasuring devices) are considered to be stored and need not be tested unless they are removed from                                                                                                                      :
the shielded mechanism.                                                                                                                                                                         l l
4.2-2                                                                                             Rev. O

r l-e ATTAsIOIENT 1                                                                       DRAFT                                        {
'                                                                                                                                                                                                                                    i TEC10lICA1, REQUIREMENT $.1 CONTAflOGNT PDIETRATION CONDUCTOR OVERCURRENT                                                                                          l PROTECTION DEVICEg NOTE:       This Technical Requirement contains the listing of overcurrent                                                                                         !
;                                                                             protection devices subject to the requirements of Specification                                                                                        j 3.8.4. Although the Specification is repeated here, care must be                                                                                       j taken not to overlook Technical Specification Requirements,                                                                                            j l                                                                                                                                                                                                                                    !
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1 5.1-1                                               Rev. O

ATTACHMENT 1                    DRAFT 3/4.8.4      ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4        The containment penetration conductor overcurrent protective devices shall be OPERABLE.
APPLICABILITY:      Mndes 1, 2. 3. and 4 ACTION:
kith one or more of the containment penetration conductor overcurrent protective device (s) inoperablet
: a. Restore the protective device to OPERABLE status ort
: 1. Deenergize the circuit (s) by racking out. locking open, or removing the iaoperable protective devica d tripping / removing the associated protective device within 72 hours, declare the      @
affected system or component inoperable, and verify the             O inoperable protective device racked out. locked open, or removed at least once per 31 days thereaf ter, the provisions of Specification 3.0.4 are not applicable to overcurrent protective devices in circuits which have their associated protective device E
sua s -
tripped / removed and their inoperable protective devfte racked    O out. locked open, or removed; or                                   g' on
: 2. Deenergine the circuit (s) by tripping / removing the associated protectiva device g racking out. locking open, or removing the inoperable protective device within 72 hovrs. declare the          @.
affected systes or component inoperable, and verify the             g associated protective device to be tripped /renoved or the          g inoperable protective dt..tec racked out. locked open, or removed  w at least once per 7 days thereafter, the provisions of              O Specification 3.0.4 are not appiteable to overcurrent protective    m' devices in circuits which have their associated protective device tripped / removed or their inoperable protective device racked out, )
g locked open, or removed or b.
N Be in at least HOT STANDBY vithin the nut 6 hours and in COLD             M' SHUTDOWN within the followins 30 hours.
g"*
SURVEILLANCE REQUIREMENTS 4.8.4       The containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
: a. At least once per 18 monthst
: 1)    By verifying that the medium voltage 6.9KV and lov voltage 480V svitchgear circuit breakers are OPERABLE by selecting, on a rotating basis, at least one or 10% of the circuit breaker (whichever is greater) of each current rating and performing the following:
5.1-2                      Rev. O

ATTACMMENT 1                   DRAFT ELECTRICAL EQUIPMENT PROTECTIVE DEVICES SURVEILLANCE REQUIREMENTS a)     A CHANNEL C/LIBRATION of the associated protective relays, b)     An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed, and                   C c)      For each circuit breaker found inoperable during these functional tests, one or an additional representative        @
                        . ample of at least 10% of all the circuit breaker of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that      @'
type have been functionally tested; and
: 2)    By selecting and functionally testing a representative sample of          '
at least 10% of each type of 480V molded case circuit breakers and lower voltage circuit breakers. Circuit breakers selected O
for functional testing shall be selected on a rotating basis.
O Testing of these circuit breakers shall consist of injecting a       g.
current with a value equal to 300% of the pickup of the long-time delay trip element and 150% of the pickup of the short-time delay 3
trip element, and verifying that the circuit breaker operates within the time delay band width for that cur ent specified by O
the manufacturer. The instantaneous element shall be tested by suma injecting a current equal to 220% of the pickup value of the element and verifying that the circuit breaker trips                 ya instantaneously with no intentional time delay. Molded case          VJ circuit breaker testing shall also follow this procedure except     'Q that generally no more than two trip elements time deley and         g instantaneous, will be involved. The instantaneous element for molded case circuit breakers shall be tested by injecting a          O current for a frame size of 250 amps or less with tolerances of      ''' '
               +40% -25% and a frame size of 400 amps or greater of 225% and verifying that the circuit breaker trips instantaneously with no     2 g
apparent time delay. Circuit breakers found inoperable during        a functional testing shall be restored to OPERABLE status prior to     M resuming operation. For each circuit breaker found inoperable during these functional tests, an additional representative          [
a sample of at least 10% of all the circuit breakers of the            w inoperable type shall aleo be functionally tested uns ',1 no more failures are found or all circuit breakers of that type have been E
functionally 1isted.
: b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recon =endations.
5.1-3                       Rev. O

,   e ATTAC10GNT 1                                                                            DRAFT     I TECHNICAL REQUIRDfENT 5. I                                                                                        <
l TAlt.E 5.1.1                                                                                      l i
CONTAINNENT PPNETRATION CONDUCTOR                                                                                      l NJrECTIVE DEVICES                                                                                                     [
f DEVICE NUMBER                                                                                                                                  SYTTEM    !
AND I.0 CATION                                                                                                                                 POWERED  !
  ,     1. 6.9 RVAC from Switchgeara                                                                                                                         !
i
: a.            Switchgear Bus lAl                                                                                                         RCP #11 l
                            !)      Primary Breaker IPCPX1                                                                                                      i t
a)   Relay 50H1-51                                                                                                          !
b)   Relay 26                                                                                                               '
c)   Relay 86M                                                                                                              i f
: 2)       Backup Mreakers IA1-1 or 1Al-2 I
a)    Relay 51M2                                                                                                             ;
b)    Relay 51 for 1Al-1 c)    Relay 51 for 1Al-2                                                                                                     l d)    Re',ay 86/1A1
: b.           Switchgear Bus 1A2                                                                                                         RCP (12   f
: 1)      Primary Breaker IPCPX2 a)    Rulay 50M1-51                                                                                                          (
b)    Relay 26                                                                                                               I c)    Relay 86M                                                                                                              i
: 2)      Backup Breakers lA2-1 or IA2-2 a)   Relay 51M2 b)   Relay 51 for IA2-1 c)   Relay 51 for 1A2-2 d)   Relay 86/1A2
: c.          Switchgear Bus IA3                                                                                                          RCP #13
: 1)      Primary Breaker IPCPX3                                                                                                       !
a)   Relay $1M1-51                                                                                                          k b)   Relay 26                                                                                                                !
c)   Relay 86M                                                                                                               !
i i
[
5.1-4                                                                                Kev. O
_         ._. - , _ __ _ - -                                              ._..._............_.......-..,~.,~_..__._-_._.._.O

l     .                                                                       ,
{
,ii' l
ATTACHNUT 1          DRA/T        l l
TECHNICAL REQUIREMENT 5.1                [
t TABLE 5.1.1 (Continued)                 i I
C0NTAINMENT PDETRATION CONDUCTOR              l l
5 DEVICE NUMBER                                            SYSTDI       I AND LOCATION                                             POWERED
: 1. 6.9 KVAC from Switchgears (Continued)                            i
: 2)    Backup Breakers 1A3-1 or 1A3-2 i
a)     Relay 51M2                                     l b)     Relay 51 for 1A3-1                             [
c)     Relay 51 for 1A3-2 d)     Relay 86/1A3
: d. Switchgear tus 1A4                             RCP #14 f
: 1)   Primary Breaker ITCPX4 f
a)      Relay 50M1-51 b)      Relay 2f                                       {
t c)      Relay 86M                                      I
\                                                                             I l                 2)   Backup Breaker 1A4-1 or 1A4-2                          l a)      Relay $1M2                                     f b)      Relay 51 for 1A4-1                             !
l                      c)      Relay 51 for 1A4-2                             i d)      Relay 86/!A4 l
t
: 2. 480 VAC from Switchgears                                         ,
1 2.1 Device Location -                               Containment  l 480V Switchgears 1EBl. 1EB2                    Recirc. Tans t IEB3 and 1EB4                                  and CRDM Vent Tans
(                 a. Primary Breakers - 13AV1                               c l                          IfNAV2. 15AV3 ITILAVd,.                            l 1FNCBI and ITNCB2                                  i i
: b. Backup Breakers - 1EB1-1                               j 1EB2-1, 1EB3-1 and 1EB4-1
: 1)     Long Time & Instantaneous Relays
* 50/51            50 gg (IEB1-1) g/51 (1EB2-1) y 50/51             50/51                         -
g 3 (1E33-1) 797;74(1EB4-1) 50/51             50/51 I15Dil (1EB3-1) M 2(IEI'"I) 5.1-5              Rev. O       ;
i

o                                                                                                                           ,
ATTACHNENT 1                                           DRAFT L                                   TECNNICAL REQUIRDfENT 5.1 t
TABLE 5.1.1 (Continued)                                                             '
CONTAINNENT PENETRATIC'd CONDUCTOR                                                            I I
t DEVICE NUMBER                                                                                  SYSTEM                 ,
AND LOCATION                                                                                   POWERED l
: 2. 460 VAC from Switchgears (Continued) l i
: 2)    Time Delay Relays                                                                               ,
t 62-1662-1X         gggg,g) 62-1662-1X (IEB2-1) 1FNAV1                                            1FMAV2                                        l 62-1662-1X         ggg gg) 62-1662-1X (1E32-1)                                                  I 1FNAV3                                            1FNAV4                                        (
l 62-1662-1X 1FNC81            (1EB3-1) 62-1662-               1FNCl2  n (1E34-1)                           i i
2.2 Device Location - 480V                                                               Containment            [
Switchgear '3B4                                                                     Polar Crane            !
t
: a. Primary Breaker - ISCCP1
: b. Backup Breaker 1EB4-1 l.
: 1)       51 ISCCP1                                                                                          [
t
: 2)       62                                                                                           !
TIN.TT
: 3. 430/AC from Mstor Control Centers 3.1 Dov'ee Location                               - MCC 1E31-2 Containment Numbers                              !
listed below.                                   l Primary and Backup                           - Both primary and backup breakers Breakers                                                  have identical trip ratings and are              (
in the same MCC Covt. These                      L breciers are General Electric type               j 1HED or THFK with thermal-magnetic               !
trip elements.                                   I
* Associated circuit breaker shown in parentheseJ; e.g. ,1EB3-1, is backed to ITNAV3 and 1TNCBl.
I 1
[
3.1-6                                               Rev. O

o ATTACHMENT 1                     DRAFT   !
TECHNICAL REQUIREMENT 5.1 TABLE 5.1.1 (Continued)                         l CONTAINMENT PENETRATION CONDUCTOR                     -
OVERCURRENT PROTECTIVE DEVICES                       t DEVICE NUMBER AND LOCAT:0N
: 3. 480VAC from Motor Control Centers (Continued)
MCC 1EB1-2              C.E.
COMPT. NO.
               ~
BKR. TYPE       SYSTEM POWERED 4G                 THED          Motor Operated Valve 1-TV-4691 4M                 THED          Motor Operated Valve 1-TV-4693 3P                 THED          Containment Drain Tank Pump-03 9H                 THED          Reactor Cavity Sump Pump-01 9h                 THED          Reactor 9avity Sump Pump-02 7H                 THED          Containment Sump fl Pump-01 7M                 THED          Containment Sump fl Pump-02 6H                 ThED          RCP #11 Motor Space Heater-01 6M                 THED          RCP #13 Motor Space Heater-03 8D                 THED          Incore Detector Drive "A" 8D                 THED          incore Detector Drive "B" 7B                 THED          Incore Detector Drive "P" 3B                 THG           Stud Tensioner Holst Outlet-01 7D                 THED         Hydraulic Deck Lift-01              i 4B                 THED         deactor Coolant Pump Motor Hoist    ,
Receptacle-42 Bli                DIED         RC Pipe Penetration Cooling Unit-01 SM                 THED         RC Pipe Penetration Cooling Unit-02 5H                 DIED         RCP 911 011 Lift Pump-01
;          SM                 THED         RCP #13 011 Lift Pump-03 l
105                THED         Preaccess P11ter Train Package l                                          Receptacle-17 5B                 THED         Containment Ltg XFMR-14 (PNL-C3) l          10P               YHED          S.C. Vet Layup Cire. Pump 01 l                                           (CPI 4.MPRP-01) l          12M               THED          S.C. Vet Layup Cire. Pump 03 l                                          (CPI-CTAPRP-03) 12H               THFK          Cont. Ltg. Transf. CPI-ELTRNT-28    !
(AULC-11AMC-12)                     i 5.1-7                        Rev. 0

o ATTACHMENT 1                     LRAFT TECHNICAL REQUIREMENT 5.1 TABLE 5.1.1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR
                                                     ~
0VERCURRENT PROTECTIVE DEVICES DEVICE NUMBER AND LOCATION
: 3.                 480VAC from Motor Control Centers .(Continued)
MCC IEB1-2                               C.E.
COMPT. NO.                            BKR. TYPE        SYSTDI POVERED 6D                    THED          kefusiing stachine (Manipulator Crane-01) 2M                    THED          RC Drain Tank Pump No. I 2F                   THED          Containment Itg XFMR-16 (PNL C7 & C9)
IM                   THED          Containment Ltg X*MR-12 (PNL Cl & C5) 3M                   THED          Preaccess Fan No, 11 3.2 Device Location        - MCC IEB2-2 Containment Numbers listed below.
Primary and Backup - Both primary and backup breakers have Breakers                identical trip ratings and e e located in                                        l the same MCC compt. These breakers are General Electric type THED and THFK with thermal-magnetic trip elements.
MCC lEB2-2                              G.E.                                                                                     I COMPT. NO.                            BKR. TYPE       SYSTEM POVERED                                                             ,
4G                    TH ED         Motor Operated Valve 1-TV-4692 4M                    THED          Motor Opsrated Valve 1-TV-4694 3F                    THED          Containment Drain Tank Pump-04                                             ;
7H                    THED          Containment Sump No. 2 Pump-03 7M                    THED          Containment Sump No. 2 Pump 04 6H                    THED          RCP No. 12 Motor Space Heater-02                                           1 6M                    THED          RCP No. 14 Motor Spact Heater-04                                           I l                                   5B                    THED          Incore Detector Drive "C"                                                  i 1
2B                    THED          Incore Detector Drive "D" 7B                    THED          Incore Detector Drive "E"                                                  ,
l                                   5D                    THED         Containment Fuel Storage Crane-01                                           '
l 1
3B                    THED         Stud Tensioner Heist Outlet-02
                                                                                                                                                   \
l                                   4B                    THED         Containment Solid Rad Waste Compactor-01 l
5.1-8                         Rev. 0

  .c ATTACHMENT 1                       DRAFT TECHNICAL REQUIRFMENT 5.1 TABLE 5.1.1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES DEVICE NUMBER AND LOCATION
: 3. 480VAC from Motor Control Centers (Continued)
MCC IEB2-2                0.E.
COMPT. NO.              BKR. TYPE        SYSTEM POWERED 10B                 THED           RCC Cha ige Fe:ture Hoist Drive-01 10F                 THED           Refuel.ng Cavity Skimmer Pump-01 12B                 THED           Pever Receptacles (Cont. E1. 841')
IM                  THED           S.C. l'et Layup Cire. Pump 02 (CPI-cFAPRP-02) 12M                  THED          S.C. Wet La>up Cire. Pump 04 (CPI /FAPRP-0()
8H                   THED          RC Pipe Penetration Fan-03 8M                   THED          RC Pipe Penetration Fan-04 5H                   THED          RCP #12 011 Lift Pump-02 SM                   THED          RCP #14 011 Lift Pump-04 12H                  THED          Preaccess Tilter Train Package Receptacles - 18                               ;
6D                   THED          Convainment A2x111ary Upper Crane-01           i 2T                   THED          Containment Ltg. XIER-13 (PNL C-2) 7D                   THED          Containment Elevator-01                        t 2D                   THED          Containment Access Rotating                    i l                                              Platform-01                                    l 2M                   THED          Reactor Coolant Drain Ta k Pump-02             I 9F                  THID           Containment Ltg. XFMER-47 (PNL C8&C10)         ,
l           9M                  THID           Containment Ltg. XFKR-15 (PNL C4&C6)           I 1                                                                                             [
3M                  THED           Preaccess Tan-12                               l IG                  THTK          Containment Welding Mschine Power               l Supply Unit                                    l 3.3 Device Location             - MCC lEB3-2 Containment numbers listed below.                                  f Primary and Backup         - Unless noted otherwise, both primary            !
Breakers                     and backup breakara have identical trip ratings and are located in the same MCC coept. These breakers are General Electric type THED or THFK with thereal-magnetic trip elements.            ;
I l
l                                           5.1-9                          Rev. 0 1
\

O e
ATTACHMENT 1                      DRAFT TEC.JiICAL REQUIRD(ENT 5.1 TABLE 5.1.1 (Continued)
CONTAINMENT PENETRATION C01 JUCTOR OVERCURRENT PROTEC*IVE DEVICES DEVICE NUMBER AND LOCATION
: 3. 480VAC from Motor Control Centers (Continued)
MCC IEB3-2                 C.E.
COMPT. NO.               BKR. TYPE       SYSTEM POWERED 8RF                   TH ED         JB-IS-1005 for Altern. Feed to Motor Operated Valve 1 a702A IG                   THED          Motor Operated Valve 1-8112 90                    THED          Motor Operated Valv- 1-8701A 9M                    THED          Motor Operated Valve 1-8701B 5M                    THED          Motor Operated Valve 1-8000A 5G                    TH ED         Motor Operated Valve 1-HV-6074 4G                    THED          Motor Operated Valve 1-HV-6076 4M                    TH ED
* Motor Operated Valve 1-HV-6078 2G                   INED           Motor Operated Valve 1-HV-4696 2M                    THED          Motor Operated Valve 1-HV-4701 3G                    THED          Motor Operated Valve 1-HV-5541 3M                   THFD           Motor Operated Valve 1-HV-5543 IM                   T'IED          Motor Operated Valve 1-HV-f*83 6F                   FIED           Motor Operated Valve 1-HV-8808A                       L 6M                   TH ED          Motor Operated Valve 1-HV 8802C 7M                   THED          Containment Ltg. XFMR-18 (PNL SCl&SC3)
BM                   THED          Neutron Detector k' ell Fan-09 7F                   THFK           Electric H Recombiner Power Supply FNL-01 BRM                  THED           Fire Protection Containment Isolation l                                             MOVI-HV-4075C l
* Primary protection is provided by Gould Tronic TR5 fusible svitch with l      3.2A fuse.
l l
l l                                          5.1-10                         Rev. O

      * ..                                                                                  i O
i LTTACNMENT 1                      DRAFT TECHNICAL REQUIRDGNT 5.1 TABLE 5.1.1 (C,ontinued)
CONTAINMENT PENETRATION CONDUCTO ,R                      f vvsatvuRaux FRCFTECTIVE DEVICQ DEVICE NUMBER                                                                    !
AND LOCATION                                                                     i t
i
: 3. 480VAC from Motor Control Centers (Continued)                              i 3.4 Device Location               - MCC 1E54-2 Csnts.inment numbere listed I below.                                 [
primary and Backup          - Unless noted otherwise, both primary Breakers                      and backup breakers have identical trip ratings and are located in the same MCC compt. These breakers are General Eltetric type W ED or THFK with thermal-sagnstic trip elements.
MCC lEB4-2                  C.E.
COMPT. HO,,               SKR. TYPE       SYJTEM POWERED IM                    NED           J3-IS-12300. Altern. Feed to Motor Operated Valve 1-87018        f 8G                    TIED          Motor Operated Valve 1-8702A l
8M                    TdED          Motor Operated Valve 1-87025           !
4M                     THED          Motor Operated Valve 1-80005           I 4C                     THED          Motor Operated Valve 1-HV-6075         !
3C                     THED          Motor Operated Valve 1-HV-6077 JM                     THED*         Motor Operated Valve 1-HV-6079 2G                    THED          Motor Operated Valve 1-HV-5562 2M                     THED          Motor Operated Valve 1-HV-5563         .
3F                     THED          Motor Operated Valve 1-88085 f
                $M                     THED          Motor Operated Valve 1-8808D           !
6M                     THED          Containment Ltg. XD0t-19 (PNL SC2&SC4) f 7M                     THED          Neutron Detector Vell Tan-10           !
j               6F                     T3FK          Elect. H Recombir.er Power Supply FNL-02
* Primary protection is prsvaded by Could Tronic TR5 fusible switch with         j 3.2A fuse.                                                                      ;
I i
I 5.1-11                          Rev. 0

O                                                                                                                      ,
ATTACHMENT 1                       DhAFT TECHNICAL REQUIREMENT 5.l_
TAB 1.E 5.1.1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRFA'T PROTECTIVE DEVICES DEVICE Nt*KBER                                                       SYSYEM AND LOCATION                                                         POVERED
: 4. 480VAC Trom Pane! boards Tor                                   Prassuriser Pressuriser Heaters                                            Heaters
: a. Primary Breakers - Gereral Electric Type TJJ Thermal Magnetic                                            !
breaker.                                                                                                 I Breaker No. & Location -      Ckt. Xos. 2 thru 4 of Panelbosrds                                          (
1EB1-1. IEB1-2, 1EB2-2, 1EB3-7..
1EB4-1,1EB4-2 and Ckt. Nos. 2 thru 5 of Pane 1 boards 1EB2-1 and IEB3-1.
l
: b. Backup Breakers - General Electric Type TMJS with longtime and insts. solid state trip devices with 400 Amp.                                         ;
sensor.                                                                                '
i t
Breaker No. & Location - Ckt. No. 1 of Pane 1 boards 1EB1-1                                              l 1EB1-2. 1EB2-1, 1EB2-2, 1EB3-1, 1EB3-2                                        t 1EB4-1 and 1EB4-2.
I
: 5. 120V Epace Heater circaits                        containment Rectre. Ten                                     l frea 480V Switchgears                             and CRDM Vent. Tan Motor                                    i Space Heaters L
: a. Primary Breakers                                                                                        i BIR. LOCATION                      VESTINCHOUSE                                                               .
       & NUMBER                           BER. TYPE                                                                  I i
Svgr. 1EBl.                        'JB 1010 Cubicle 3A                                                                                                   ''
CP1-VATNAV-02 Space Heater Bkr.
Svgr. 1EB2                         EB1010 Cubicle 3A CVP1-VATNAV-02 Space Heater Bkc.
Svgr. 1EB3                        EB1010 Cubicle 9A CP1-VATNAV-03 Space Heater Bkr.
5.1-12                           Rev. O

    .h' O
ATTAC10fENT 1                                        DRAFT TECHNICAL REQUIREMEN" 5.1 TABLE 5.1.1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
: 5. 120V Space Heater Circuits from 480V Switchgears (Continued)
BKR. LOCATION                                                                     VESTINGHOUSE
           & NUMBER                                                                       , 3KR. TYPE Swgr. IEB4,                                                                       EB1010 Cubicla 9A CPI-VAFNAV-04 Swgr. IEB3,                                                                       EB1010 Cubicle 8A, CP1-VAFNCB-01 Space Heater Bkr.
: b. Backup Breakers BKR. LOCATION                                                                     GENERAL ELECTRIC
           & NUMBER                                                                          BKk. TYPE Panel IEC3-2                                                                      TED Ckt. No. 3 Panel IEC3-2                                                                      TED Ckt. No. 4 Panel IEC4-2                                                                      TED Ckt. No. 3 Panel 1EC4-2                                                                      TED Ckt. No. 4
: 6. 125V DC Lighting                                                                  Emerge
* icy DC Lighting
: a. Primary Breaker BREAKER LOCATION                                                                  G.E. Bkr.
AND NUMBER                                                                        TYPE DC Panelboard                                                                     TFJ 1D2-1, Ckt #6
: b. Backup Device - N/A (Fuse) 5.1-13                                          Rev. 0 l                          _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _

e                                                                                                                                                                l
  ~,
D ATTACHMENT 1                                                  DRAFT TECHNICAL REQUIREMENT Sd TABLE 5.1.1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES DEVICE NUMBER AND LCCATION
: 7.            125V DC Control Power                         various
: a.        Primary Devices - N/A (Fuse)
: b.        Backup Breakers GENERAL ELECTRIC PANELBOARD NO.                           CKT. NO.                                      BREAKER TYPE XED1-1                         1,6,7,8,9.10                                                TED XED2-1                        1,3,6,7,8,9,10                                              TED XD2-3                         8,9,12,14,17                                                TED 1ED2-1                        7,10,12,15,16,17                                            TED 1EDI-1                        7,10,14,17                                                  TED             .
1D2-3                         7,10,11,14,17                                               TED XD2-1                          11                                                         TED
: 8.             11SV AC Instrument Distribution Panel Board 1C3-3
: a.         Primary Devices - N/A (Fuses)
: b.         Backup Breaker - GE Type TED located in Instrument                                                                    '
Distribution Panel Board IC3-CKill
: 9.            120V AC Power for Personnel and Emergency Airlocks
: a.         Primary Devices - N/A (Fuses)
: b.          Backup BreikeTs GENERAL ELECTRIC PANELBOARD NO.                   CKT          NO.                                        BREAKER TYPE                             ,
XEC2                        34                                                       TED XEC1-2                          2                                                    TED L
t' r
5.1-14                                                  Rev. 0
       ._ __ _,__ .___.--._,, _- , - . _ __. -_                           - - _ - -        . . ~ _ - _ _ _ . - _ - . . - . . .              , . . - . . - , . _ _ _ -

_r n
ATTAChifENT 1               DRAFT
: 10. 118V AC Control Power
: a. Primary Devices - N/A (Fuses)
: b. Backup Breakers CENERAL ELECTRIC PANELBOARD NO.              CKT. NO.              BREAKER TYPE XEC1-1                 3.5,7,9,10,12                TED XEC2-1                 3,5,7.9,10,12                TED                        :
IC2                    12,22                        TED                        1 1C3                    12,14                        TED 1PCI                   10,13                        TED                        i IPC2                   10                           TED 1PC4                   6,10                         T ED IEC1                   3,4,8,9                      TED 1EC2                   3,4,7,9                      TED 1EC5                   3,8                          TED 1EC6                   3,8                          ten
: 11. Emergency Evacuation fratem Warning Lights Power
: a. Primary Devices - N/A (Fuses)
: b. Backup Breakers SQUARE D SINGLE POLE M ELB0ARD NO.              CKT. NO.                   BREAKER TYPE XEC3                      3                     FAL-12020 XEC4                      3                     FAL-12020
: 12. DRPI Data Cabinet Power Supplies
: a. Primary Devices - N/A (Fuses)
: b. Backup Breakers CENERAL ELECTRIC PANELBOARD NO.             CKT. NO.               BREAKER TYPE l                       IC14                      1,2                        TED
;             BASES r
5.2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES The bases for OPERABILITY and surveillance of these devices are contained in the CPSES Technical Specifications.
All Clasa 1E motor-operated valves' motor starters are provided with thermal overload protection which is permanently bypassed and provides an                '
alarm function only at Comanche Peak Steam Electric Station. Therefore, there are no OPER*BILITY or Surveillance Requirements for these devices, since they will not prevent safety-related valves from performing their function (refer to Regulatory Cuide 1.106, "Thermal Overload Protection for Electric Hotors on Motor Operated Valves," Revision 1, March 1977).                      ;
5.1-15                   Rev. 0
                                                                                           ,, - _----%}}