ML18152A436

Proposed Tech Specs Re ESF Instrument Allowed Outage Times & Operator Actions

ML18152A436
Person / Time
Site:	Surry
Issue date:	11/08/1990
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18152A437	List: ML18152A436 ML18153C598
References
NUDOCS 9104170217
Download: ML18152A436 (22)

Text

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• ATTACHMENT 2 SURRY POWER STATION UNITS l AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE ESF INSTRUMENT AOTs AND OPERATOR ACTIONS /~04:L 70217-,;,,~: ' PDR A.[11:,,::K 0!30002:~:o

P PDR

-*

• 3. 7 INSTRUMENTATION SYSTEMS Qperatiooal Safety Instrumentation.

Applicability

• Applies to rec;1.ctoi' and safety features instrumentation systems. Objectives TS 3.7-1 To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety. Specjficatioo A For on-line testing or in the event of a subsystem instrumentation channel failure, plant operation at rated power shall be permitted to continue in accordance with TS Tables 3.7-1 through 3.7-3. B. The reactor trip system instrumentation channels and interlocks shall be operable as specified in TS Table 3.7-1. C. The Engineered Safeguards Actions and Isolation Function Instrumentation channels and interlocks shall be operable as specified in TS Tables 3.7-2 and 3.7*3 respectively.

D. The Engineered Safety Features initiation instrumentation setting limits shall be as stated in TS Table 3.7-4. E. The explosive gas monitoring instrumentation channels shown in Table 3.7-S(a) shall be operable with their alarm/trip setpoints set to ensure that the limits of Specification

3. 11 .A. 1 are not exceeded.

1. With an explosive gas monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, declare the channel inoperable and take the action shown in Table 3.7-5(a).

e e TS 3.7-2 2. With less than the minimum number of explosive gas monitoring instrumentation channels operable, take the action shown in Table 3. 7-S(a). Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission (Region II) to e.xplain why this inoperability was not corrected in a timely manner. F. The accident monitoring instrumentation for its associated operable components listed in TS Table 3.7-6 shall be operable in accordance with the following:

1. With the number of operable accident monitoring instrumentation channels less than the total number of channels shown in TS Table 3.7-6 items 1 through 10, either restore the inoperablej channel(s) to operable status within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 2. With the number of operable accident monitoring instrumentation channels less than the minimum channels operable requirement of TS Table 3.7-6 items 1 through 10, either restore the inoperablef channel(s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. G. Deleted H. The containment hydrogen analyzers and associated support equipment shall be operable in accordance with the following:

1. A reactor shall not be made critical nor* be operated at power without two i"ndependent containment h*ydrogen analyzers operable.

2. During power operation or return to criticality from hot shutdown conditions, the following restrictions apply: a. With one hydrogen analyzer inoperable, restore the inoperable analyzer to operable status within 30 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. With both hydrogen analyzers inoperable, restore at least one analyzer to operable status within 7 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Note: Operability of the hydrogen analyzers includes proper operation of the res~ive Heat Tracing System.

e DELETE PAGES 3.7-2 a and b TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERA TING CONDITIONS FUNCTIONAL, UNIT TOTAL NUMBER OF CHANNELS 17. Low saeam generator waler level wilh steanvteedwater How nismalch 2/loop-level and 2/loop-flow msmalCh 18. 19. 20. A. Reactor Trip Breakers B. Reactor Trip Bypass Breakers -Nole C Automatic Trip Logic ReadOf Trip Sy&aem lnlelloc*s

-Nole D a. Intermediate range neutron tut, P-6 b. Low power reac&or trips block, P-7 Power range neutron llux, P-10 and Turbine iq,ul&e pressure c. Power range neutron flux, P-8 d. Power range neutron tux, P-10 ** T Ulbine impulse pressure 2 2 2 2 .. 2 .. .. 2 MINIMUM OPERABLE CHANNELS 1/loop-level and flow msmatch or 2/loop-level and 1/loop-llow msmatch 2 1 2 2 3 2 3 3 2 CHANNELS TO IBIP 1/loop-level coincident with llow mismatch in same loop* 1 1 1 1 2 1 2 2 1 PERMISSIBLE BYPASS CONQIJIONS Note c -With the Reactor Trip Breaker open lor surveillance testing in accordance with Specification Table 4.1-1 (Item 30) Note o -Reactor Trip SySlem Interlocks are described in Table 4.1-A . OPERATOR ACTION Ill 7 8 11 13 e 13 13 13 13 13 -t C/J w ...... * .... N e TS 3.7*13b ,, TABLE 3. 7-1 (Continued)

ACTION 4. .. With the number of channels OPERABLE one less than required by the Minimum OPERABLE Channels requirement

• and with the THERMAL POWER level: ACTIONS. a. Below P-6, {Block of Source Range Reactor Trip) setpoint.

restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b. Above P-6, operation may continue.

With the number of channels OPERABLE one less than required by the Minimum OPERABLE Channels requirement, verify compliance with the SHUTDOWN MARGIN requirements within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 6.A. With the number of OPERABLE Channels equal to the Minimum Operable Channels requirement, REACTOR CRITICAL and POWER OPERATION may proceed provided the following conditions are satisfied:

1. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 2. The Minimum OPERABLE Channels requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification

4. 1 . -6. B. With the number of OPERABLE Channels one less than required by the Minimum Operable Channels requirement, be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e TS 3.7-13c ... TABLE 3. 7-1 (Continued)

ACTION 7. ,

• With the number of OPERABLE Channels equal to the Minimum Operable Channels, REACTOR CRITICAL and POWER OPERATION may proceed provided the following conditions are satisfied:

1. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 2. The Minimum OPERABLE Channels requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification

4.1. ACTION

8.A. With the number of OPERABLE Channels one less than the

• Minimum Channels OPERABLE requirement, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. In conditions of operation other than REACTOR CRITICAL or POWER OPERATIONS, with the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour. However, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification

4.1 provided

the other channel is OPERABLE.

8. B. With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and apply Action 8.A. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required tor performing maintenance to restore the breaker to OPERABLE status.

.J ACTION 9. e TS 3.7-13d TABLE 3. 7-1 (Continued)

With .. one channel inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or reduce THERMAL POWER to below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coo*1ant Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Operation below P-8 may continue pursuant to ACTION 1 o. ACTION 10. With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 11. With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SHUTDOWN within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. In conditions of operation other than REACTOR CRITICAL or POWER OPERATIONS, with the number of OPERABLE Channels one less . than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour. However, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification

4.1 provided

the other channel is OPERABLE.

ACTION 12. With the number of OPERABLE channels less than the total number of channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 13. With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the -existing plant condition, or be in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

( TABLE 3.7-2 ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS MINIMUM TOTAL NUMBER OPERABLE CHANNELS PERMISSIBLE OPERATO FUNCTIONAL YltJ OF CHANNELS CHANNELS JO TRIP BYPASS CONDITIONS ACTIONS 1. SAFETY INJECTION a MaflJal 2 2 1 21 b.' High coriainment pressure 4 3 3 17 C. High ditterential pressure 3/steam line 2/sleam line 2/sleam line Primary pressure less 20 between any steam line on any lhan 2000 psig, except and lhe steam header sleamline when reaclor is critical d. Pressurizer low pressure 3 2 2 Primary pressure less 20 than 2000 psig, except when reactor is critical e. HQ\ steam flow in 2/3 steam 11188 coincident wilh low T avg or law steam Ille pressure 1) S&eam line How 2/steamline 1/steam line 1/steam line Reactor coolant T avg 20 any two lines less lhan 543° during heatup and cooldown 2) Tavg 1/loop 1/loop 1/loop Reactor coolanl T avg 20 any two loops any two loOpS less than 543° during heatup and cooldown 3) Steam line pressure 1/line 1/line any 1/line any Reactor coolant T avg 20 two loops two loops less lhan 543° during healup and cooldown Automalic actuation logic 2 2 1 14 '. CJ) *~ ...., * .... ..

' TABLE 3.7-2 (Conlinued)

ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS

' FUNCTIONAL UNIT 2. CCNTAINMENT SPRAY a Maooal b. High containment pressure (Hi-HI) c. Automatic actuation IOgic 3. AUXILIARY FEEDWATER a Sleam generaaor water level law-low TOTAL NUMBER OF CHANNELS 1 set 4 2 1) Start mo&or driven pumps 3/steam generator

2) Starts turbine driven pump 3/steam generator

b. RCP undervolage starts 3 tulbine driven puq> MINIMUM OPERABLE CHANNELS 1 set 3 2 2/sleam generator 2/steam generator 2 CHANNELS TO IBIP 1 set* 3. 1 2/steam generator any 1 generator 2/steam generator any 2 generators 2 PERMISSIBLE BYPASS CONDITIONS

c. Safety injection

-start l1IDIOl driven puR1)5 See #1 above (aJ.1 SI initialing lunclions and requirements)

d. Slalion btackOul -start molOr driven pu111>s 1/bus 2 transler buses/unil

• Musi acluaae 2 sw1lches simullaneously 1/bus 2 transler buses/unit 2 I. OPERATOR ACJlONS 15 17 14 20 20 20 21 * ( -i en w ...... * .... "' ' I TABLE 3.7-2 (Continued)

ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS FUNCTIONAL YNIJ AUXILIARY FEEOWATER (oonainued)

e. Trip ol main feedwaler puq,s -Slart motor driven puq,s f. Aulomalic acaualion logic 4. LOSS OF POWER TOTAL NUMBER OF CHANNELS 2/MFW pulfl) 2 a 4. 16 kv emergency bus 3/bus undervohage (loss of volage) b. 4.16 kv emergency bus 3/bus undefvolage (degraded volage). 5. NON-ESSENTIAL SERVICE WATER ISOLATION

a. low intake canal level 6. ENGINEEREDSAFEGUAROS ACTUATION INTEfl..OCKS

-Nole A a. Pressurizer pressure, P-11 b. Low-iow T avg, P-12 c. Reac&or llip, P...f 4 3 3 2 MINIMUM OPERABLE CHANNELS 1/MfWpump 2 2/bus 2/bus 3 2 2 2 Nole A -Engineered Safeguards Aclualion lnlerlocks are described in Table 4.1-A CHANNELS TO TRIP 2-1 each MFWpuflll 1 2/bus 2/bus 3 2 2 1 PERMISSIBLE OPERATOR BYPASS CONQIJIONS ACTIONS 21 22 20 20 20 23 23 24 -f en .~ ...., I -CJ)

.. .. TABLE 3.7-3 INSTRUMENT OPERA TING CONDITIONS FOR ISOLATION FUNCTIONS FUNCTIONAL UNIT 1 . CONTAINMENT ISOlA TION a Phasel 1) Salety lf1iedk>n

2) Automatic inilialion logic 3) Manual b. Phase 2 1) High conlainmenl pressure 2) Aulomatic actuation logic 3) Manual C. Pha&e3 1) High contairvnenl pressure (Hi-Hi setpon) 2) Automalie actuation logic 3) Maooal 2. STEAMLINE ISOLATION TOTAL NUMBER OF CHANNELS MINIMUM OPERABLE CHANNELS CHANNELS JO JBIP PERMISSIBLE OPERATOR BYPASS CONDITIONS ACTIONS See Item 11, Table 3. 7-2 (all SI inilialing funclions and requiremenls) 2 2 4 2 2 4 2 1 set 2 2 3 2 2 3 2 1 set 1 1 3 1 1 3 1 1 se1* 14 21 17 14 15 17 14 15 a High steam ttow in 213 lines See Uem #1.e Table 3.7-2 for operabilily requiremenls oolnddefll with 2/3 low T avg or 2/3 low &aeam pressures

• Musi actuate 2 switches simubaneously

-; C/) ......, * ...6 ......,

TABLE 3.7-3 (Continued)

INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS FUNCTIONAL UN1I STEAMLINE ISOLATION (coooooed)

b. High conlairvnent pressure (Hi-Hi setpoint)

c. Manual d. Automatic actuation logic 3. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam generator waler-level high-high

b. Automatic actuation logic and actualion relay c.

• Sal81y injection TOTAL NUMBER Of CHANNELS 4 1 /sleamline 2 3/steam generator 2 MINIMUM OPERABLE CHANNELS 3 1/steamline 2 2/steam generator 2 CHANNELS TO TRIP 3 1 /steamline 1 2/in any one steam generator 1 PERMISSIBLE BYPASS CONDITIONS See Item 11 ol Table 3.7-2 (aU SI initiating functions and requirements)

OPERATOR_

I ACTIONS-17 21 22 20 22 ...... OI -

e e TS 3.7-17b l TABLES 3.7-2 ANO 3.7*3 TABLE NOTATIONS ACTION 14. With the number of OPERABLE channels one less than the Minimum

• Channels OPERABLE requirement, be in at least HOT SHUTDOWN

• within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. One channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.1, provided the other channel is OPERABLE.

ACTION 15. With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ACTION 17. With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.1 . ACTION 19. With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 20. With the number of OPERABLE channels one less than the Total Number of Channels, REACTOR CRITICAL and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b. The minimum channels OPERABLE requirement is met; however. the inoperable channel may* be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per specification 4.1.

.J .. e TABLES 3.7-2 ANO 3.7-3 TABLE NOTATIONS (Continued)

TS 3.7-17c I-ACTION 21. With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirements, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ACTION 22. With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SHUTDOWN within 1 O hours and reduce pressure and temperature to less than 450 psig and 350° within the following 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification

4.1 provided

the other channel is OPERABLE.

ACTION 23. With less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window(s) that the interlock is in its r~uired state for the existing plant condition, or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 24. With the number of OPERABLE channels less than the total number of channels, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or reduce pressure and temperature to less than 450 psig and 350° within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

e TS 4.1-1 4.1 OPERATIONAL SAFETY REVIEW Applicability Applies to item~ directly related to safety limits and limiting conditions for operation.

Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.

Specification A.

• Calibration, testing, and checking of instrumentation channels and interlocks shall be performed as detailed in Table 4.1-1 and 4.1-2. B. Equipment tests shall be conducted as detailed below and in Table 4. 1-2A. 1 . Each Pressurizer PORV shall be demonstrated operable:

• a. At least once per 31 days by performance of a channel functional test, excluding valve operation, and b. At least once per 18 months by performance of a channel calibration.

2. Each Pressurizer PORV block valve shall be demonstrated operable at least once per 92 days by operating the valve through one complete cycle of full travel. l I I TABLE 4.1-1 (Continued)

MINIMUM ~REOUENC!ES FOR CHECK CAUBAATIONS AND TEST OF INSTRUMENT CHANNELS CbaooelP@scriQtiQD Calibrate

]ffl Remarks 39. Sleamlfeedwat,r Flow and Low SIG s A M Water Level 40. Intake Canal Low (See Footnote 1) D A M(1), 1) Logic Test 0(2) 2) Channel Electronics Test 41. Turbine Trip and Feedwater Isolation

a. Steam generator waler level high s A M b. Aulomatic actualion logic and aclualion relay N.A. N.A. M 42. Reactor Trip System lnler1ocks a Intermediate range neutron N.A. A(3) M(4) 3) Neutron detectors may be excluded from flux, P-6 lhe calibration

b. Low power reacaor trips block, P-7 N.A. A(3) M(4) 4) Wilh power greater than or equal 10 lhe Power range neutron Hux, P-8 interlock selpoinl, the required lesa shaU C. N.A. A(3) M(4) consist of verifying lhal the interlock is d. Power range neutron flux, P-10 N.A. A(3) M(4) in lhe required slate by observing lhe perrrissive annunciator window e. Turbine impulse pressure N.A. A A Footnote 1: Consists of verifying tor an inmcaled intake canal level greater lhan 23'-6* lhal all four low level sensor channel alarms are not in an alarm slale. Cajjbraliop Consi&ls of uncovering lhe level sensor and measuring lhe lime response and vollage signals for lhe immersed and dry conditions.

h also verifies proper action of inslrumenl channel from sensor lo eleclronics lo channel oulpul relays and annunciator.

Only the IWO available sensors on lhe shuldQwn unil would be lesled. 1) The logic lesl verifies lhe three oul of four logic development tor each lrain by using lhe channel 1es1 swilches for lhal lrain. 2) Channel electronics tesl verifies lhal electronics module responds properly lo a superimposed diflerenrial millivoll signal which is equivalent lo the sensor detecting a *dry" condition.

• e _.. ' O> a TABLE 4.1-1 (Continued)

MINIMUM FREOUENCJES FOR CHECK. CAUBAATlONS AND JEST OF INSTRUMENT CHANNELS Channel pescoplion

43. Engineered Safeguards Aclualion lnlertocks

a. Reactor trip, P-4 b. Pressurizer pressure, P-11 c. Low, low Tavg, P-12 S

• Each Shill D

• 0., N.A.

• Not Applicable Q -Every 90 eHedive fuU power days

• See Specificalion 4.1.D N.A. N.A. N.A. CaMbrate N.A. A A A A A Aemadss M -Monlhly P -Prior lo each slartup it not done within the previous week A -Each Refueling Shuldown i '* * -

DES!GNAJION Reactor Trip (P-4) lnlermediate Range Neutron Fk.lx (P-6) Power Range Neutron Flux (P-10) Low Power Reactor T,.>> Block (P-7) TABLE 4 J-A REACTOR TRIP SYSTEM AND ENGINEERED SAFEGUARDS ACTION INTERLOCKS CONDITION FUNCTION , 1 ol 2 bleakers open 1 of 2 Intermediate range above setpoint (increasing power level) 2 of 2 Intermediate range below setpoint (decreasing power level) 2 of 4 Power range above setpoint (increasing power level) 3 of 4 Power range below selpoinl (decreasing power level) 2 of 4 Power range above setpoint or 1 of 2 Turbine lff1)Ulse chamber above &elpOinl (Power level increasing) 3 of 4 Power range below selpOint and 2 o, 2 Turbine lq>ulse charmer pressure below setpoinl (Power level decreasing)

Aeact_or tripped -actuates turbine trip, allows aulo closing of mam teedwater valves on T avg below selpoinl, prevents lhe opening qt lhe main teedwaler valves w,hich were closed by a safely injection or high steam generator waler level signal. . Alows manual block of source range reactor lrip. Automatically defeals lhe block of source range reactor lrip. Allows manual block of power range (low selpoinl) and inlennediale range reactor trips and intermediate range rod stop. AutomalicaUy blocks source range reactor trip. Automatically defeats the block of power range (low selpOinl) and intermediale range reactor lrips and inlennediale range rod slop. 1'1)UI lo P-7. Alows reactor trip on: Low flow or reactor coolant pu~ I breakers open in more than one loop, Undervollage (RCP busses), Undertrequency (ACP busses), Turbine Trip, Pressurizer low pressure, and Pressurizer high level. Prevents reactor trip on: Low flow or reactor coolant pu~ breakers open in more lhan one loop, Undervollage (ACP busses), Undertrequency (ACP busses), Turbine Trip, Pressurizer low pressure, and Pressurizer high level. " /.. ,, .. e QESIGNAJION Power Range Neutron flux (P-8) Pressurizer Pressure (P-11) Low, Low Tavg (P-12) TABLE 4,1-A (contjnyed}

l;JEACJOR IBIP SYSTEM AND ENGINEERED SAFEGUARDS ACTION INTERLOCKS CONQIJJON 2 ot 41 Power range above selpoinl (Power level increasing) 3 of 41 Power range below selpojnt (Power level decreasing) 2 of 3 Pressurizer pressure above selpoinl (increasing pressure) 2 of 3 Pressurizer pressure below selpoinl (decreasing pressure) 2 of 3 T avg above selpoinl (lefll)eralure increasing) 2 of 3 T avg below selpoinl (lefll)eralure decreasing)

FUNCTION Permil reaclor trip on low flow or reaclor coolant pufll> breaker open in a single loop. . . Blocks reacror lrip on low flow or reaclor coolanl pufll> breaker open in a single loop. On increasing pressurizer pressure, P-11 automatically reinstates safely injection actualion on low pressurizer pressure.

On decreasing pressure, P-11 allows lhe manual block of safely injection actuation on low pressurizer pressure.

On increasing primary coolant loop te~rature, P-12 automatically reinstates safely injeclion aclualion on . high sleam flow coincident with eilher low-low T avg or low Sleam ine pressure, and provides an arming signal lo lhe Sleam dump syslem. On decleasing primary coolant loop te~ralure, P-12 allows the manual block of safely injection actuation on high steam flpw coincidenl with either low-low T avg or low sleam ine pressure and automalically removes the anning signal from the Sleam dump system. I t r:. *! .....

• m CD }

1. 2. 3. TABLE 4.1-1A RADIQ6CJ:ntE LICUID EffLUfti!I M~ITORING IMSIBUMfliTATIOO SUBllflL~~E BEOUIBEMEtUS

' CHANNEL QESCRIPJIQN Gross Radioactivity Monitors Pn>vidng Alarm and Au1omatic T eminalion ot Release (a,) Liquid Radwasle Ettluenl Line Gross Beta or Ganvna Aadioactivily Monilors Providing Alarm but nol Providing Aulomalic T eminalion ot Release (a,) Circulating Waler Discharge Line (b) Coq>onent Cooing Service Water Sylllem EHluenl Une Flow Raia Mau. aremenl Oe\fices Uquid RUNa&&e Effklen Line D -oat, M

• Monthly R -Each Refuelng Shutd0wn a -Ouarte,ty PR -Prior to each release N.A.

• Nol Aflplicable CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CAUBRAIIQN FUNCTIONAL TEST 0 PR A a 0 M R a 0 M R a 0 N.A. A N.A. *

• e e -J

. j .. l; TABLE 4.1-18 RAotOACJIVE*GASEous EFFLUENT MCNIWBING lNSTRUMENTAJ!ON SURVEILLANCE REOUIBEMENJS CHANNEL QESC81PJICN CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CAUBRAJION FUNCTK>NAL TEST 1 . Process Vent Syaaem ' (8' Noble Gas Activity Monilor Pro\liding Alarm and Automalic Teminalion ol Release (b) Iodine Saq,ler (C) Particulale

$aq)ler (d) Process Vent Flow Rate Monilor (e) Saq)ler Flow Rate Measuring Device 2. Wasle Gas Hotdup Syslem Explosive Gas Moniloring Syslem (a) Hydrogen Monilor (b) Oxygen MonilOr 3. Condenser Ajr Ejeelor Syslem (8' GIOs& Aclivily Moniot (b) Mr Ejec1or Flow Rale Measuring Device 4. Venli1alion Vent SySlem (8' Noble Gas Aclivily Monitor (b) loclne 5anl>ler (c) Particulale Saq>ler (d) Ventilation Vena Flow Rale MonilOr (e) San1)ler Flow Rate Measure Device 0 w w 0 0 0 D 0 0 0 w w 0 0 M* N.A. N.A. N.A. N.A. N.A. N.A. M N.A. M N.A. N.A. N.A. N.A. A N.A. N.A. A SA Q( 1) 0(2) A A A N.A. N.A. A SA (1) The channel calibralion

&hall inckJde lhe use ol slandard gas samples containing a nominal: 1. one volume percent hydrogen.

balance nilrogen, and 2. four volume percenl hydlogen, balance nilrogen.

(2) The channel calibration shal Include lhe use ol slandard gas saq>tes conlaining a nominal: 1. one volume percenl oxygen. balance nitrogen, and 2. four vok.lme percent oxygen, balance riitrogen.

D -Daily W -Weekly M -Monlhly R -Each Refueling Shuldown SA -Semi-annually NA -Nol Applicable a -Quarterly

• -Monlhly and prior lo each Waste Gas Decay Tank Release a N.A. N.A. N.A. N.A. M M a N.A. a N.A. N.A. N.A. N.A. .. , . e .... "' ...... co