ML20049K064
| ML20049K064 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/18/1982 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20049K054 | List: |
| References | |
| NUDOCS 8203290363 | |
| Download: ML20049K064 (43) | |
Text
.
ENCLOSURE Safety Evaluation for Unit 2 Technical Specification Revision
Background
Subsequent to issuance of the Unit 2 Technical Specifications, the NRC requested that Alabama Power Company update the Unit 1 Technical Specifications to be consistent with those in Unit
- 2. As part of the Unit 1 update effort, additional improvements in the Technical Specifications were incorporated that were beyond those in the current version of the Unit 2 Technical Specifications. Accordingly, the Unit 2 Technical Specifications were reviewed with respect to the improvements and changes proposed.
References:
(1) FNP Unit 1 Technical Specifications, Amendment 26 (2) FNP Unit 2 Technical Specifications, Amendment 11 Bases:
The proposed Unit 2 Technical Specifications will result in clarification of requirements and incorporate improvements from t
the revised Unit 1 Technical Specifications ( Amendment 26) and f rom the NRC Standa rd Technical Specifications. The proposed Unit 2 Technical Specifications are consistent with the plant safety analysis, Amendment 26 of the Unit 1 Technical Specifications, and previous agreements with the NRC.
Conclusion:
The proposed changes to the Unit 2 Technical Specifications do not involve an unreviewed safety question as defined by 10 CFR 50.59.
9203290363 820318 PDR ADOCK 05000364 P PDR
( -
TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
. M At least once per 31 days At least once per 92 days.
Q SA At least once per 184 days.
A At least once. per 365' alays, l R
At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each releise.
( N.A. Not applicable.
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1.2 560 0.6 0.8 1.0 0.2 0.4 0 ) FRACTION OF RATED THERMAL POWER t Figure 2.11 Reactor Core Safety Limit . Three Loops in Operation APPLICABIt.ITY: 65% STEAM GEAERAToR TU8E F FARLEY-UNIT 2 2-2
r N APPLICABILITY SURVEILLANCE REQUIREMENTS l
- 1. At least HOT STANDBY within the next 6 hours, At least HOT SHUTDOWN within the following 6 hours, and l
- 2. '
- 3. At least COLD SHUTDOWN within the subsequent 24 hours.
Thisspecificationisnotapplicableinh40 DES 5or6. 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveillance 1.nterval,and . . . .
- b. The combined time interval for any 3 consecutive surveillance intervals ~
not to exceed 3.25 times the specified surveil' lterval.
!i 4.0.3 Failure to perform a Surveillance Requiremendwithin the specified tiine N interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exceptions Surveillance to these requirements are stated Requirements do not have to be in the individual specifications.
performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance , interval or as othenvise specified. l 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicabic Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as )
follows in these Technical Specifications:
-$ Open determination tha.t tic _ sorveilknte. had bem inadverbtY omitt4 ,_
the.5erveittance.Requiremt s611 be_ socc.essfully persrud wiWn W_ 13mitig Conditiert of Operation (Lco')pec{cd ditk Woold bep upovg di$coVerf. FARLEY-UNIT 2 3/4 0-2
POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F q [Z1 LIMITING CONDITION FOR OPERATION f 3.2.2 F q(Z) shall be limited'by the following relationships: 2 31 Fq (Z) 1 [3raf] [K(Z)] for P > 0.5 l Fq (Z) 1-[ '.62] [K(Z)] for P i 0.5 l
- where P = RATED THERMAL POWER (HERMAL POWER and K(Z) is the function obtained from Figure (3.2-2) for a given core height location.
APPLICARILITY: MODE 1
~
ACTION: With Fq (Z) exceeding its limit: 'ws Reduce THERMAL POWER at least 1% for each 1% Fn(Z) exceeds the limit _' a. within 15 minutes and similiarly reduce the Power Range Neutron I Flux-High Trip Setpoints within the next 4 hours; POWER OPERATION l may proceed for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower delta T Trip Setpoints have been The reduced at least 1% for each 1% F o (Z) exceeds the limit. Overpower delta T Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.
- b. Identify and correct the cause of the out of limit condition prior to increcsing THERMAL. POWER above the reduced limit required by a, above; THERMAL POWER may then be increased providednF (Z) is demonstrated through incore mapping to be within its Timit.
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FARLEY-UNIT 2 3/4 2-4
d TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION b MINIMUM G CHANNELS APPLICABLE 1 TOTAL NO. CHANNELS MODES ACTION TO TRIP OPERABLE . E OF CHANNELS Z - FUNCTIONAL UNIT 2 1, 2, and
- 12 1
2
- 1. Manual Reactor Trip ,
g Power Range, Heutron Flux 2 3 1, 2 2,
- 2. 4 2 A. High 2 3 2 4
B. Low # 1, 2 2 2 3 4
- 3. Power Range, Neutron Flux High Positive Rate #
1, 2 2 2 3 4
- 4. Power Range, Neutron Flux, High Negative Rate ##U 1 2 1, 2, and
- 3 2
$ 5. Intermediate Range, Neutron Flux
' 6.
- Source Range, Neutron Flux 2,,, 2#g, and
- 4 b Startup 2 1 1 3, 4 and 5 5 A. 2 0
- 8. Shutdown '
g 5 1, 2 7
- 7. Overtemperature AT 3 2 2 9
Three Loop Operation 1** 2 1, 2 3 Two Loop Operation g 1, 2 7
- 8. Overpower AT 2 2 Three Loop 0peration 3 1, 2 9 1** 2 3
Two Loop Operation #
- 9. Pressurizer Pressure-Low 3 2 2 1$ 7 l
1, 2 7 2 2 3
- 10. Pressurizer Pressure--High
, '% .)
g (r'- n
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., D TABLE 3.3-1 (Continued)
A REACTOR TRIP SYSTEM INSTRUMENTATION m MINIMUM 1 CHANNELS CHANNELS APPLICABLE E TOTAL NO. i TO TRIP OPERABLE MODES ACTION Z FUNCTIONAL UNIT OF CHANNELS i m 2 2 Ig 7,
- 11. Pressurizer Water Level--High 3 Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1 7 l 12. A. each oper-any oper-j (Above P-8) ating loop ating loop 2/ loop in 2/ loop 1 7 B. Loss of Flow - Two Loops 3/ loop two oper- each oper-(Above P-7 and below P-8) ating loops ating loop 3/ loop 2/ loop in 2/ loop in 1, 2 7
- 13. Steam Generator Water each oper-4 Level--Low-Low any oper-
- ating loops ating loop 2/ loop-level 1/ loop-level 1/ loop-level 1, 2 7
- 14. Steam /Feedwater Flow Mismatch and Low Steam and coincident and 2/ loop-flow with 2/ loop-flow Generator Water Level mismatch in mismatch in 1/ loop-flow ,
same loop mismatch in same loop or same loop 2/ loop-level and 1/ loop-flow mismat?hin same loop
- 15. Undervoltage-Reactor Coolant 1 7 8
3-2/ bus 2 2 Pumps
- 16. Underfrequency-Reactor Coolant 7 8
3-2/ bus 2 - 2 1 Pumps
TA'BLE 3.3-1 (Continued) TABLE NOTATION d' 1 a With the reactor trip system breakers in the closed position, the control
. , rod drive system capable of rod' withdrawal, and fuel in the reactor The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.
# The provisions of Specification 3.0.4 are not applicable.
" High voltage to detector may be de-energized above P-6.
' # " Indication only.
" " The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level > 10% cf RATED THERMAL POWER.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than required by , the Minimum Channels OPERABLE requirement, be in HOT STANDBY l within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1. . ACTION 2N0mber - Withofthe number of OPERABLE channels one less than the T Channels, STARTUP and/or POWER OPERATION may proceed '.' provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour.
The Minimum Channels OPERABLE requirement is met; however,
- b. I ne twegemiele.for :::surveillance dditf:' :1 channel may be bypassed for up to 2 hoursl testing 3per Specification 4.3.1.1.
of %e. o%er channels
- c. Either, THERHAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to less than or equal to 85%
of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours.
- d. The QUADRANT POWER TILT RATIO, as indicated by the remaining three detectors, is verified consistent with the quadrant power distribution obtained by using the movable incore detectors in the four pairs of symmetric thimble locations at least once per 12 hours when THERMAL POWER is greater than 75% of RATED THERMAL POWER.
b ,) e FARLEY-UNIT 2 3/4 3-6
TABLE 4.3-1 S REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS
& CHANNEL M00ES IN WHICH 5
- CHANNEL, CHANNEL FUNCTIONAL SURVEILLANCE TEST REQUIRED
" CHECK CALIBRATION FUNCTIONAL UNIT N.A. S/U(1) N.A.
Manual Reactor Trip N.A. .
- 1. ,
- 2. Power Range, Neutron Flux D(2),N(3) M 1, 2 S
A. High and Q(6) D(2),N(3) S/U(10) 2 S B. Low and Q(6) M 1, 2 Power Range, Neutron Flux, N.A. R(6) 3. High Positive Rate M 1, 2 Power Range, Neutron Flux, N.A. R(6) R 4. High Negative Rate [ S/U(1) 1, 2, and
- Intermediate Range, S R(6) b 5.
Neutron Flux S(7) R(6) M and S/U(1) 2, 3, 4; .
- 6. Source Range, Neutron Flux 5, and l
R M 1, 2 S
- 7. Overtemperatura AT R M 1, 2 S
- 8. Overpower ai
- 9. Pressurizer Pressure--Low S R M IM I R M 3, 2
- 10. Pressurizer Pressure--High S
- 11. Pressurizer Water level--High S R M 1h 5 H 1 Loss of Flow - Single Loop S R
- 12. A.
- i. H.A. 1 Loss of Flow - Two Loops S R
! R. l l y ; ')
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TABLE 3.3-3 (Continuedl A _ ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATIO E MINIMUM 1 APPLICABLE CHANNELS E TOTAL NO. CHANNELS MODES _ ACTION OPERABLE Z OF CHANNELS TO TRIP _ m FUNCTIONAL UNIT i 4. STEAM LINE ISOLATION 1/ steam line 1/ operating 1, [3 22 Manual 1/ steam line steam line a. 2 1, h 3 21 1 2
- b. Automatic Actuation Logic
'2 3 1, h3 14 3
- c. Containment Pressure--
High-High 1, [3 ) w d. Steam Flow in Two A Steam Lines--High 3 1/ steam line 14 W Three Loops 2/ steam line 1/ steam line A any 2 steam
- Operating lines 15 ,
/any 1/ operating Two Loops 2/ operating 1 steam line steam line operating -
Operating steam line g 1 ,3 COINCIDENT WITH T ,yg--Lo d ow 14* Three Loops 1 T,yg any 1 T,yg any 1 T ,yg/ loop Operating 2 loops 2 loops H Two loops 1Tavg/oper 1 T,yg i T,yg in any Operating operating loop ating loop in any oper-ating loop , 9 i
TABLE 3.3-3 (Continued) ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION y
=
MINIMUM CHANNELS CHANNELS APPLICA8tE Z TOTAL NO. TO TRIP OPERABLE MODES ACTION to FUNCTIONAL UNIT OF CHANNELS
- e. Steam Line Pressure-1, 3"JN Low
' A 1 pressure 1 pressure 14 Three Loops 1 pressure /
Operating loop any 2 loops any 2 loops pressure 1 pressure 15 Two Loops 1 pressure / 1 Operating operating in any oper- any operating loop ating loop loop
- 5. TURBINE TRIP &
FEEDWATER ISOLATION A
- a. Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2g 14 l any oper- each oper- l y Water Level--
ating loop ating loop g High-High i 6 g,,
's
TABLE 3.3-3 (Continued) ) l
/ TABLE NOTATION \
Q.)
#Trip function may be bypassed in this MODE below the P-11.
(Pressurizer Pressure Block of Safety Injection) setpoint.
" Trip function say be bypassed in this MODE below P-12.
(T,yg Block of Safety Injection) setpoint.
# The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.
*The provisions of Specification 3.0.4 are not applicable.
Mf*Nof ayliahIe e'V mae% sfeam isola %m volveS Me clo.se ACTION STATEMENTS RN3tE reguitemt$ Meheum PERABLEchannfisonelessthanthegda+ ACTION 13 - With the number o
" -i:r ;f Channels be in HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1 provided the other channel ,
is OPERABLE. (' ACTION 14Number - Withofthe number of OPERABLE channels one less than the To Channels, operation may proceed until performance (t of the next required CHANNEL FUNCTIONAL TEST provided the
~.
inoperable channel is placed in the tripped condition w' thin 1 hour. ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in at least HOT STANDBY within the next 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification i 4.3.2.1. ! ACTION 16 - With Number of the number Channels, of OPERABLE operation channels may proceed provided the one less than th inoperable channel is placed in the bypassed condition and the Minimum l Channels OPERABLE requirement ise;==t=d it..i.. I Mtrrp met g one additional channel may be bypassed for up to 2 hours for sprveillane testing per W ecification 4.3.2.1. ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed. OPERh6LG cepiremt ;_ ACTION 18 - With the number of OPERABLE Channels tne less than th ( " d :r Of Channels restore the inoperable channel to PERABLE g status within 48 hours or be in at least HOT STANDBY within the t .I
'# next 6 hours and in COLD SHUTDOWN within the following 30 hours.
I f FARLEY-UNIT 2 3/4 3-23
TABLE 3.3-3 (Continued) ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION say proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour. -
- b. TheMinimumChannelsOPERABLErequirementXismet;however, the. kp%W surveillance channel may be bypassed testinoper for 4.3.2.1.
Specification up to 2 hours for L ef ochu channel.s ACTION 20 - With the interlo'ck inoperable to the extent that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the appropriate ACTION statement (s) of Table 3.3-3 for the affected function (s). i Interlock Affected Channels on Table 3.3-3
- 1. P-4 a. Pressurizer Pressure - Low _
- 2. P a. Steam Line Pressure - Low
- b. Steam Flow in Two Steam Lines High ,
\
Coincident With T - Low-Low 4'y w OPERABLE requiremenfV9 'j ACTION 21 - With the number OPERABLE Channels one less than the fuuME N Channels, be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however; one channel may be bypassed for up to 2 hours for surveillance testing provided the other channel is OPERABLE. ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. ACTION 23 - With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST. 5
~s
.j I FARLEY-UNIT 2 3/4 3-24 l
f TABLE 4.3-2 (Continued) n ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION rn SURVEILLANCE REQUIREMENTS CHANNEL MDDES IN WHICN b . CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 4 CHECK CALIBRATION TEST REQUIRED N FUNCTIONAL UNIT . *
- 6. AUXILIARY FEEDWATER N.A. 1, 2, 3
- a. Automatic Actuation Logic N.A. M(2)((o)
R M 1,2,3 Steam Generator Water 5
; b.
Level--LorLow f X N,/, R M 1
- c. Undervoltage - RCP
! See 1 above (all SI surveillance requirements)-
- d. S.I.
l N.A. N.A. S/U(5) 1
- e. Trip of Main Feedwater l [ - Pucps, ,,
, 4. m
- 7. LOSS OF POWER N.A. R(3) M(4) 1, 2, 3, 4 -
- a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)
N.A. R(3) M(4) 1, 2, 3, 4
- b. 4.16 kv Emergency Bus J
Undervoltage (Degraded Voltage) M.A. R N.A.
- 8. ENGINEERED SAFETY FEATURE N.A.
ACTUATION SYSTEM INTERLOCKS
? 'j t i \ >,
TABLE 4.2-2 (Continued) TABLE NOTATION L(2. D (1) Manual actuation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days. (2) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (3) Channel calibration shall exclude actuation of the final trip actuation relay.* (4) Functional testing shall consist of verification of relay operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay." (5) If not performed in the previous 92 days. (lo) 6xcluchng gutop,ghc, ,gcfvaYion loglc be idg oh Amln l heedwdec (sv a(s. A (
- n. -
\
l l
" Actuation of the final trip actuation relay shall be included in response time testing.
\ i :> FARLEY-UNIT 2 3/4 3-37
TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION s MINIMUM E MEASUREMENT CilANNELS APPLICABLE ALARM / TRIP O y INSTRUMENT OPERABLE MODES SEIPOINT RANGE ACTION
- 1. AREA MONITORS m 10-1 -104mR/hr
- a. Fuel Storage Pool 1 (a) $ 15 mR/hr 23 Area (R-5)
- b. Containment Area (R-27A&B) 2 1,2,3,4 N/A 1 - 107 R/hr 27a
- 2. PROCESS MONITORS
- a. Fuel Storage Pool Area Gaseous Activity-
- Ventilation System -3 pCi/cc(c) 10-106cpm 25 (b) $ 8.73 x 10 Isolation (R-25A&B) 1 R
- b. Containment Y i. Gaseous Activity-M a) Purge & Exhaust -2 0 26 1,2,3 (d) cpm Isolation (R-24A&B) 1 6 2.27 x 10
$ 2.27 x 10,2pCi/cc(c) pCl/cc(c) 10-10 4,S,6 (d) 26 1,2,3,4,5,6 (e) 1 4.54 x 10_ pCi/cc(c) 26 1 2.27 x 10 pCi/cc(c) 1,2,3,4,5,6 (f) 26 0 24 I 1.2,3 & 4 N/A 10-10 cpu b) RCS LeakaDe h" Detection (R-12)
- 11. Particulate Activity R
RCS Leakage 1 1,2,3 & 4 N/A 10-106 cpm 24 2
% Detection (R-11) z
- c. Control Room P
1,2,3h,4and $ 800 cpm 10-106 cpm 27 Isolation (R35A&B) 1 during movement of irradiated fuel or movement of loads over irradiated fuel
TABLE 3.3-6 (Continued) N ACTION STATEMENTS J ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at
, least once per 24 hours.
ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1. ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12 and 3.9.13. ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9. ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode eitheof operation. required W hannels less than the a Minimum ACTION 27a - With' the number of OPERABLEChannels OPERABLE requir / to. OP.ERABLE status within -7z--.. l
- n .., 1 M _ .c ^
- ': x y - 2 1 W :_E ;_n 858"* 72. 6ours , or: .
0 Initiate %c preplannel alternaie me.thed d an'brs.g
%c aferoPrinte- paraweted.s), and
- 2) Prepan ad submit. a. Spee.ial Report to the Commissan pursuast to Spee.;p;eagen G,q 2. Qts;n .tise. next I4 days 6 flow lng %e event outlining %e action %len,% cause of' Eke, inoperAbi(ily and the plang dHJ sclt edu/c. fo r PCS t.ori$ he syslem to OPERABLE stat.uJ ,
- a. With fuel in storage pool.
- b. With irradiated fuel in the storage pool.
- c. Above background with no flow.
- d. With mini purge in operation. )
- e. With slow speed main purge in operation. .
f. With fast speed main purge in operation.
-FARLEY-UNIT 2 3/4 3-40
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^'
, m.
- l. TABLE 4..__
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH m SURVEILLANCE T CHANNEL CHANNEL FUNCTIONAL REQUIRED E CALIBRATION TEST CHECK _ ! Z INSTRUMENT < w
- 1. AREA MONITORS R M S
- a. Fuel Storage Pool Area '
(R-5) 1,2,3,4 R N/A S
- b. Containment Area (R-27A&B)
- 2. PROCESS MONITORS
- a. Fuel Storage Pool Area
' Gaseous Activity - ** Ventilation System R M S ' Isolation (R-25 A&B) , y b. Containment Gaseous Activity i. , y a) Purge & Exhaust M All MODES
- S R
" Isolation (R-24 A&B)
M 1,2,3 & 4 , S R b) RCS Leakage Detection (R-12)
- 11. Particulate Activity M 1,2,3 & 4 S R RCS Leakage Detection (R-ll) 1,2, nd during R M
- c. Control Room Isolation S movement of irradiated
! fuel or movement of loads over irradiated fuel With fuel in the storage pool or building. With irradiated fuel in the storage pool. i e
O ,, TABLE 3.3-L , 1n iE ACCIDENT MONITORING INSTRUMENTATION 5 11 MINIMUM E REQUIRED CHANNELS U NUMBER OF CHANNELS OPERABLE .
- N INSTRUMENT Reactor Coolant Outlet Temperature-T Hot-Wide Range 2 1 1.
. 1
- 2. Reactor Coolant Inlet Temperature-TCold-Wide Range 2 Reactor Coolant Pressure-Wide Range 2 1 3.
Steam Generator Water Level-Wide Range or Narrow Range 2/ steam generator 1/ steam generator 4. Hefueling Water Storage Tank Water Level 2 1 5. 2 1 j 6. Containment Pressure 2 1 l$ 7. Pressurizer Water Level 2/ steam generator 1/ steam generator
- 8. Steam Line Pressure 2 l'
- 9. Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor 2 1
- 10. ,
PORV Position 'ndicator 1/ valve 1/ valve 011. PORV Block Valve Position Indicator 1/ valve 1/ valve Q*12. L dication '
- 13. Safety Valve Position hieter-(One ckenel is, a// valve 1/ valve l Posi&n indicolor and a cJww.wl s's dischage.tegeratore) l Containment Water Level-Narrow Range 2 1 14.
Containment Water Level-Wide Range 2 1 15. Incore Thermocouples 4/ core quadrant 2/ tre quadrant 16.
"Not applicable if'the associated block valve is in the closed position.
, **Not applicable if the block valve is verified in the closed position and power removed, i
TABLE 4.3-7 A ACCIDENT MCNITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS' E CHANNEL CHANNEL 7 CHECK CALIBRATION E INSTRUMENT Q - M R w 1. Reactor Coolant Outlet Temperature-THot Wide Range R
- 2. Reactor Coolant Temperature-TCold -Wide Range M M R i'
- 3. Reactor Coolant Pressure-Wide Range
- 4. Steam Generator Water Level- Wide Range or R Narrow Range M M R
- 5. Refueling Water Storage Tank Water Level M R
- 6. Containment Pressure M R y 7. Pressurizer Water Level M R Y 8. Steam Line Pressure E M R
- 9. Auxiliary Feedwater Flow Rate
- 10. Reactor Coolant System Subcooling R Margin Monitor .M M R
*11. PORV Position Indicator M R A*12. PORV Block Valve Position Indicator Yndication
- 13. Safety Valve Position E d ;;'.:r M R l
M R
- 14. Containment Water Level-Harrow Range M R
- 15. Containment Water Level-Wide Range M R 16 Incore Thermocouples "Not applicable if the associated block valve is in the closed position.
**Not applicable if the block valve is verified in the closed position and power removed. 4
INSTRUMENTATICN FIRE DETECTION INSTRUMENTATION k(.'s LIMITING CONDITION FOR OPERATION 3.3 3.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-12 shall be OPERABLE. APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE. ACTION: With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-12:
- a. Within 1 hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s-) is located inside the containment, then monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5. -
- b. Restore the inoperable instrument (s) to OPERABLE status within 14 days; or in lieu of any other report required by Specifi-
.{ cation 6.9.1, prepare and submit a Special Report to the Commission N pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS fest aero5oI l 4.3.3.9.1 Ea of the above required fire detection instruments which are accessible d ing plant operation shall be demonstrated OPERABLE at least once per 6 month by performance of a function test which includes subjecting the a detector to gants Fire detectors which are not accessible during plant 5 operation shall be demonstrated OPERABLE by the performance of this functional test during each COLD SHUTDOWN exceeding 24 hours unless performed in the previous 6 months. 4.3.3.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. FARLEY-UNIT 2 3/4 3-59
REACTOR COOLANT SYSTEM / COLD SHUTDOWN v LIMITING CONDITION FOR OPERATION 3.4.1.4 a. Two# residual heat removal (RHR) loops shall be OPERABLE
- and at least one RHR loop shall be in operation.**
APPLICABILITY: MODE 5. " ACTION:
- a. With less than the above required RHR/ Reactor Coolant loops OPERABLE, immediately initiate corrective action to return the required RHR/ Reactor coolant loops to OPERABLE status as soon as possible.
- b. With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
SURVEILLANCE REQUIREMENTS
\
4.4.1.4 At least one RHR loop shall be determined to be in operation and circulating reactor ccoint at least once per 12 hours. S:
^The normal or emergency power source may be inoperable in MODE 5.
f:r ^^"--:-cr c ' """ .c .;ill er.x g g i: ' :; = 5?: f; .,, .. ^ hv . m......
**The RHR loop may be removed from operation for up to 2 hours provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
# Three filled Reactor Co.olant loops and at least two steam generators having levels greater than or equal to 10% of wide range indication may be substituted for one RHR loop.
N A Reactor Coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 310 F unless (1) the pressurizer water volume is less than 770 cubic feet (24% of wide range, cold, pressurizer level indication) or (2) the secondary water tem-( perature of each steam generator is less than 50 F above each of the Reactor f- . ( Coolant System cold leg temperatures. FARLEY-UNIT 2 3/4 4-4a
REACTOR COOLANT SYSTEM
, S I
3/4.4.5 RELIEFVALVJJ LIMITING CONDITION FOR OPERATION 3.4.5 All power relief valves (PORVs) and their associated block valves shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTION:
- a. With one or more PORV(s) inoperable, within 1 hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With one or more block valve (s) inoperable, within 1 hour either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); othemise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
./
- c. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l 4.4.5.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION and operating the valve through one cycle of full travel. , 4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per l 92 days by operating the valve through one complete cycle of full trav J tie. AC. Tion requirements of a. above . s
~
EACTOR COOLANT SYSTEM , ( OPERATIONAL LEMAGE , , LIMITING CONDITIO?. FOR OPERATION
- 3. 4.7. 2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. 1 GPM UNIDENTIFIED LEAKAGE, .
- c. 1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator,
- d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and
- e. 31 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235
- 20 psig.
. f. 1 GRM leakage from any Reactor Coolant System Pressure Isolation Valve s fied ia Table 3.4-1 at a Reactor Coolant System pressure of 223 0 psig.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTCOWN within the following 30 hours. .
- c. With any Reactor Coolant System Pressure Isolation Valve leakage l
greater that 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 within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REOUIREMENTS
-= -
4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within ' each of the above limits by;
- a. Monitoring the containment atmosphere particulate radioactivity monitor at least once par 12 hours.
- b. Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours.
FARLEY-UNIT 2 _ 3/4 4-17
C- PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE. . APPLICABILITY: MODES 1, 2 and 3. ACTION:
- MODE 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is eith;r restored to'- OT reloce.
OPERABLE status :: ::: n d within 4 hours; otherwise, i:
- 0T?f. 'aY "'"'- th:
- t : h;.c; ;c.d i- :;;T ,; uT;;Z ithir th:
S?? :'. ; S h:: :. fewec to \ess %w or egual to 5% of RAT 60 THERMAL YoicE~A wo'%in (o hours., MODES 2 - With one main steam line isolation valve inoperable, subsequent l-and 3 operation in MODES $ 2 or 3 may proceed provided the isolation ' fvalve if :!;i:E:d ?;xd; otherwise, be in HOT STANDBY within the f next 6 hours and in HOT SHUTDOWN withir. the following 6 hours. The provisions of Specification 3.0.4 are not applicable.
- s'fuhs or closd tuoYn Y hours,
-' -rebuted +o OPEf$GLE a-SiEr edeciwg Mot >C- 2 SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steara line isolation valve shall be demonstrated OPE ,
l by verifying full closure within 5 seconds when tested pursuant to Specifica 4.0.5. 5 iO 3/4 7-9 FARLEY-UNIT 2
4 ..a .
'P1 ANT SYSTEMS
( . 3/4.7.5 RIVER WATER SYSTEM . . . LIMITING CONDITION FOR OPERATION 3.7.5 At least two independent river water loops shall be OPERABLE with at least two river water pumps per loop. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: 7MYS Withonlyone(riverwaterloopOPERABLE,restoreatleasttwoloopstoOPERABLE status withinVM or be in at least HOT STANDBY within the next 6 hours [
! and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 4.7.5 Each river water loop shall be demonstrated OPERABLE: ( .
- a. At least once per 31 days by verifying that each valve (manual, power operated or automatic), in the flow path, servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position. , ,
- b. At least once per 18 months during shutdown, by:
- 1. Verifying that each automatic valve servicing safety relate'd equipment actuates to its correct position on a low pond level signal.
l
- 2. Verifying that the buried piping is leak tight by a visual inspection of the ground area.
l e (; . i
PLANT SYSTEMS (. l i
. SURVEILLANCE REQUIREMENTS (Continued) ;
- b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tionsofdamageorimpairedOPERABILITYd(2)attachmentstothe foundation or supporting structure are securey aN
' h._
. _" 1.mah.
amadudgmemkm6sessuusps Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of , establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per However, when Specifications 4.7.9.d or 4.7.9.e. as applicable. the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and :annot be determined g OPERABLE via functional testing All snubbers connected to an l inoperable common hydraulic flui reservoir shall be counted as inoperab,le snubbers. unless -the_ test i.s sinrte.J dth ne_ pish In
%c as feond setting, utedM Ge. pisk md in
(' ' c. Functional Tests %e temics and compression mcBe. direcitoar, n, a pr n t've s le t st ce er m ng but ! [Ef t t i ea tp f be in n ep nt i h e
- ThMU i all f c 1 nal te ei w c oe ri ot eet 1
e fun ion t { L o ach e bb di ' na Sp if'c i 4. . or .7 ., e ce iter ly este un 1n j (.5 ce n uPt N o ha t of ub er hall e c fai res ef d or ti a1 nu rs av ee n 1 1 1-
.t te ,
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers l in the representative sample shall include snubbers from the following three categories:
- 1. The first snubber away from each reactor vessel nozzle
- 2. Snubbers within five feet of heavy equipment (valve, pump, turbine, motor,etc.)
- 3. Snubbers within ten feet of the discharge from a safety relief valve FARLEY-UNIT 2 3/4 7-21
Insert to 4.7.9.c At least once per 18 months during shutdown, a representative sample of 88 snubbers shall be functionally tested either in place or in a bench test. If more than 3 snubbers do not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an additional sample selected according to the expression 22 (a-3) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the initial representative sample. Functional testing shall continue according to the expression (22) b where b is the number of snubbers found inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Tables 3.7-4a and 3.7-4b have been functionally tested. Snubbers greater than 50,000 lb. capacity may not be excluded f rom functional testing requirements.* l
- This portion of the specification is not effective until the second refueling outage or when a commercial in-place testing device is available, whichever is later.
i l l
PLANT SYSTEMS x' SURVEILLANCE REQUIREMENTS (Continued) e. MechanicalSnubbersFunctionalTestAcceptanceCriteriaN
/
The mechanical snubber functional test shall verify that: I
- 1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum
"-'--'""-'""'----"-er: thr 55 l ,
drag force.
'.=t h ni te..t. l
-'=: th: h:t Activation (restraining action) is achieved within the specified 2.
range f ;; h :it; a n = h r:t hr in both tension and compression. l
- 3. Snubber release rate, where required, is within specifically For snubbers the specified range in compression or tension.
required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified. _ i .- l ( I ] f l 1 NTkts porf,'on ok -H1e spect-Sica+ ion is efSeck g ( to My follow;wg h secoacf refuehn3
/
M+or ov nge. 3/4 7-23 FARLEY-UNIT 2
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES ((. , OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. Two physically independent circuits from the offsite transmission network to the switchyard and two physically independerit circuits from the switchyard to the onsite Class IE distribution systesi, and DG 1-2A
- b. Two separate and independent diesel generator sets (Set A:
and DG-1C, Set B: DG-)lr and DG-2C) each with: l 26 Separate day tanks containing a minimum volume of 900 gallons 1. of fuel for the 4075 kw diesel generators and 700 gallons of fuel for the 2850 kw diesel generators.
- 2. A separate fuel transfer pump for each diesel.
- c. A fuel storage system consisting of four, independent stomge tanks each containing a minimum of 25,000 gallons of fuel.*
APPLICABILITY _: MODES 1, 2, 3 and 4.
' ( ACTION:
inoperable, demonstrate the OPERABILITY of ) a. ~ With an offsite circuitithe remaining offsite A.C. source by performing ment 4.8.1.1.1.a within 8 hours and at least once per 24 hours 2 SE P., , thereafter, and performing Surveillance Requirement 4.8.1.1. .a s items 1, 2, 3, 4, and 6 on diesel generators 1-2A and Jff within 8 hours unless so::h surveillance has been performed within the pre-vious 7 days. Restore at least two offsite circuits to OPERABLE status within,7 days or be in at least HOT STANDBY within the next The 6 hours and in COLD SHUTDOWN within the following 30 hours.
' provisions of Specification 3.0.4 are not applicable.
b. With one diesel generator set inoperable for reasons other than the ye scheduled maintenance ** demonstrate the operability of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 8 hours and at least once per 72 hours thereafter, and per-forming Surveillance Requirement 4.8.1.1.2.a. items 1, 2, 3, 4, and
'One operable fuel storage tank must be available for each required diesel generator.
**If this scheduled maintenance exceeds 10 days, the diesel generator
(. - declared inoperable. { % 3/4 8-1
""=;;g:,;
FARLEY-UNIT /
ELECTRICAL POWER SYSTEMS ACTION (Continued) 6 on two* diesel generators within 12 hours. Restore the diesel generator set to OPERABLE status within 18 days or be in at least HOT SHUTDOWN within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. The provisions of Specification 3.0.4 are not applicable if only one of the four diesel generator units is inoperable.
- p. With one offsite circuit and one diesel generator set of the above required A.C. electrical power sources inoperable for reasons other than the yearly scheduled maintenance,** demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Surveillance Require-ment 4.8.1.1.1.a within 2 hours and performing Surveillance Requirement 4.8.1.1.2.a. items 1, 2, 3, 4, and 6 on two* diesel generators within 12 hours. Restore at least one of the inoperable sources to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore the other AC power source (offsite circuit or diesel generator set) to OPERABLE status in accordance with the provisions of Section 3.8.1.1 Action Statements a or b, as appropriate.
- d. With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of both diesel generator sets by per-
- forming Surveillance Requirement 4.8.1.1.2.a within 2 hours; unless the diesel generators are already operating; restore at least one of ' the inoperable offsite sources to OPERABLE status within 24 hours or With only one be in at least HOT STANDBY within the next 6 hours. offsite source restored, restore both offsite circuits to OPERABLE status within 7 days from time of initial loss or be in at least HOT STANDBY within the next 6 hours aad in COLD SHUTDOWN within the following 30 hours. e." With both of the above required diesel generator sets inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by per-forming Surveillance Requirement 4.8.1.1.1.a within 2 hours and performing Surveillance Requirement 4.8.1.1.2.a, items 1, 2, 3, 4, and 6 on one diesel generator in a diesel set on the other' Unit within 8 hours; restore at least one of the inoperable diesel gen-erator sets to OPERABLE status:
'The two diesel generators chosen to be tested shall verify that at least one train of LOCA/ shutdown loads is capable of being powered at each Unit.
**1f this scheduled maintenance exceeds 10 days, the diesel generator set must be declared inoperable. )
1
- 2. .
h FARLEY-UNITg 3/4 8-2
ELECTRICAL P')WER SYSTEMS ( ACTION (Continued)
- 1. Within 24 hours or be in at least HOT STANDBY within the next 6 hours if (DG 1-2A and DG-2C) or(DG-Jif and DG-1C) or (DG-1C and DG-2C) are inoperable; or g6
- 2. Within 8 hours or be in at least HOT STANDBY within the next 6 hours if DG 1-2A and DG- are inoperable; or
- 3. Within 2 hours or be in at least HOT STANDBY within the next 6 hours if three or more diesel generators are inoperable.
Restore both diesel generator sets to OPERABLE status within 18 days from time of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:
- a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and f b. Deomonstrated OPERABLE at least once per 18 months during shutdown by transferring unit power supply from the normal circuit to the alternate circuit.
(. 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
~
- a. In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:
- 1. Verifying the fuel level in the day tank.
- 2. Verifying the fuel level 1,n the fuel storage tanks.
- 3. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.
- 4. Verifying the diesel starts and accelerates to at least 900 rpm for the 2850 kw generator and 514 rpm for the 4075 kw generators in less than or equal to 12 seconds. The generator voltage and frequency shall be > 3952 volts and > 57 Hz within 12 seconds after the start signal and operates Tor 5 minutes.
- 5. Verifying the generator is synchronized, loaded to 2700-2850 kw for the 2850 kw generator and 3875-4075 kw for the 4075 kw generator and operates for greater than or equal to 60 minutes.
c 2 FARLEY-UNIT g 3/4 8-3 h
~~
ELECTRICAL POWER SYSTEMS I SURVEILLANCE REQUIREMENTS (Continued)
- 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
- b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits specified in Table 1 of ASTM 0975-74 when checked for viscosity, water and sediment,
- c. At least once per 18 months by:
- 1. Subjecting the diesel to an inspection and maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations,
- 2. Simulating a loss of offsite power by itself, and:
a) Verifying de-energization of the 2mergency busses and load shedding from the emergency buss.; . b) Verifying the diesel starts on the auto-start signal, energizes the eg}ergency busses with permanently connected loads within 12' seconds, energizes the auto-connected l shutdown loads through the load sequencer and operates for 8 greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization of all loads, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 1 420 volts and 60 i 1.2 Nz during this test.
~
- 3. Verifying that on a Safety Injection test signal (without less l
,? of offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 I
minutes. The generator voltage and frequancy shall be > 3952 volts and > 57 Hz within 12 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained between 4160 1 420 volts and 60 1 1.2 Hz during this test.
- 4. Simulating a loss of offsite power in conjunction with a Safety Injection test signal, and:
a) Verifying de-energization of the emergency busses and load shedding from the , emergency busses. , b) Verifying the diesel starts on the auto-start signal, energizes the e ergency busses with permanently connected loads within 12 econds, energizes the auto-connected emergency (accident) loads through the load sequencer and Y 6nergladhen of M OHW 1 e egency lous Or cl'esel generdor
" / 8-4 fk==;;; ;;;. ;
FARLEY-UNIT /
ELECTRICAL POWER SYSTEMS ( SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 1 420 volts and 60 i 1.2 Hz during this test. c) . Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.
- 5. Verify that the diesel enerators operate for 24 hours while loaded to 4353 kw for the 4075 kw diesels and 3100 for the 2850 kw diesels (2000 hour rating). After completing this 24-hour test, manually trip the diesel generator from the 2000-hour load and demonstrate hot restart capability by performing Surveillance Requirement 4.8.1.1.2.a.4 within 10 minutes.
- 6. Verifying that the auto-connected loads to each diesel genera-tor do not exceed the 2000-hour rating of 4353 kw for the 4075 3
kw generator and 3100 kw for the 2850 kw generator. fx
- 7. Verifying the diesel generator's capability to:
l ~ a) Synchronize with the offsite power source while the genera-tor is loaded with its emergency loads upon a simulated restoration of offsite power. b) Transfer its loads to the offsite power source, and c) Be restored to its standby status.
- 8. Verifying that with the diesel generators operating in a test l mode (connected to its bus), a simulated safety injection signal overrides the test mode by returning the diesel gen-erator to standby operation.
Verifying that the automatic load sequence timer is OPERABLE l 9. with each load sequence time within i 10% of its required value or 0.5 seconds whichever is greater. Verifying that the following diesel generator lockout features l 10. prevent diesel generator starting only when required: a) Oil Temperature High (OTH) ( ( 1 A:;;;;;;;g ;;^. ^;
~FARLEY-UNIT / 3/4 8-5 o
~~'
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b) Coolant Temperature High (CTH) c) Coolant Pressure Low (CPL) d) Crankcase Pressure High (CCPH)
- 11. Verifying the capability to reject a load of greater than or equal to the largest single load associated with that diesel generator (approximately 1000 kw); while maintaining voltage between 3740 and 4580 volts and speed less than or equal to 75%
of the difference between nominal speed and the overspeed trip setpoint.
- d. At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, and verifying that the diesel generators accelerate to at least 900 rpm, for the 2850 kw generator and 514 rpm for the 4075 kw generator, in less than or equal to 12 seconds. l
- e. At least once per 5 years, on a staggered basis, by verifying that the diesel generator can reject a load of 1200-2400 kw without tripping. The diesel generator output breaker (s) must remain closed '
such that the diesel generator is connected to at least one emergency ' bus. Verify that all fuses and breakers on the energized emergency bus (es) are not tripped. The generator voltage shall remain within 3330 and 4990 volts during and following the load rejection. 4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall be reported to the Commission pursuant to Specification 6.9.1. Reports of diesel generator failures shall include the information recommended in Regu-latory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If
. the number of failures in the last 100 valid tests (on a per diesel basis) is '
greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1. August 1977. s' 2 3 ??2::::; ;;;. ^0 FARLEY-UNIT,2" - 3/4 8-6
TABLE 4.8-1 DIESEL _ GENERATOR TEST SCHEDULE (PER DIESEll N' umber of Failures In Test Frequency Last 100 Valid Tests *_ At least once per 14 days 12 At least once per 7 days
?.3 .
i (- (
- Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1 August 197/, where the last 100 tests are determined on a per diesel basis. For the purposes of this test schedule, only valid tests conducted after the OL issuance date shall be included in the computation ,
of the "last 100 valid tests." 8-1 o ?""."E'!!-'
" 5
( 3/4 4-6e FARLEY-UNIT / l \ _ _ _
ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. One circuit between the offsite transmission network to the switchyard and from the switchyard to the onsite Class 1E distribution system, and
- b. . ,
-amhMs
- 1. A day tank containing a minimum volume of 900 gallons for the 4075 kw generator and 700 gallons for the 2850 kw diesel Generator,
- 2. A fuel storage tank containing a minimum volume of 25,000 gallons of fuel, and
- 3. A. fuel transfer pump. .~.,
/
- s. APPLICABILITY: MODES 5 and 6.
ACTION: , With less than the above minimum required A.C. electrical power sources O suspend all operations involving CORE A.c., ALTERATIONS or fositive reacti eledrlcA j changesg udit the. rniniMom required tb oPERAGLE stAius . l SURVEILLANCE REQUIREMENTS
- 4. 8.1. 2 The above required A.C. electrical power sources shall be demonstr 1 OPERABLE by the performance of each of the Surveillance Requirem 4.8.1.1.21(exceptforrequirement4.8.1.1.2.a.51,-
Amendment No. 1 3/4 8-8 FARLEY-UN*.T 2 '
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENT 5 (Continued)
^
_.,__:_g_.!b.':'__.____!__",__...___ tusses i 2.% The voltage of each connected cell is greater than or equal to 2.02 volts under float charge and has not decreased more than I c.11 pet volts from the value observed during the original accept-ance test, I
- 3. K The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is greater than or equal to 1.190 and has not decreased more than 0.08 from the value observed I during the previous test, and
- 4. K The total battery terminal voltage is greater than or equal to 121.2 volts, a s
- c. At least once per 18 months by verifying that:
T
- 1. The cells, cell plates and battery racks show no visual j indication of physical damage or abnormal deterioration,
- 2. The cell-to-cell and terminal connections are clean, tight, and
' coated with anti-corrosion material, and _; 7, 3.[ The battery charger will supply at least 536 amperes at
> 125 volts for at least 4 hours.
- d. At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours when the battery is subjected to a battery service test or the individual cell voltage does not decrease below 1.75 volts when the battery is subjected to the following equivalent load profile.
Order In Which Duration Loads Are Current (amps) (min.)_ Applied 1 1 920 58 430 2 1 ' 920 3 59 430 4 1 920 5 3/4 8-12 FARLEY-UNIT 2
ELECTRICAL POWER SYSTEMS
, SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING
~
LIMITING CONDITION FOR OPERATION 1 1 3.8.2.5 The following D.C. distribution systems shall be energized and { J OPERABLE: TRAIN "A" consisting of 125-volt D.C. Distribution Cabinet 2M, 125-volt , battery bank No. I and a full capacity charger. TRAIN "B" consisting of 125-volt D.C. Distribution Cabinet 2N,125-volt battery bank No. 2 and a full capacity charger. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: teniw With one 125-volt D.C. distribution y;tr inoperable, restore the inoperable l distribution system to OPERABLE and energized status within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.8.2.5.1 Each D.C. hve train shall be determined OPERA 1LE and energized at l 1 east once per 7 days by verifying correct breaker alignment and indicated power availability,_ ... ... ....... ..... , .. ...._. ......oc w... .. 4el-2 .d t;. , 4.8.2.5.2 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that:
- 1. The electrolyte level of each pilot cell is between the minimum and maximum level indication marks,
- 2. The pilot cell specific gravity, corrected to 77'F and full electrolyte level, is greater than or equal to 1.190, end-
- 3. Thepilotcellvoltageisgreaterthanorequalto2.02 volts 3and 4, The total bat}ery fremiHal yoHage is gredter h or egual to
- b. At least once per 92 ays by verifying that: g 11 ,2 voll S .
- 1. The electrolyte level of each cell is between the minimum and 7 maximum level indication marks, l
a FARLEY-UNIT 2 3/4 8-15
l
\
a ELECTRICAL POWER SYSTEMS
,./
SURVEILLANCE REQUIREMENTS (Continued)
~
m The voltage of each connected cell is greater than or equal to
~
2.% 2.02 volts under float charge and has not decreased more than o,i .SpeE volts from the value observed during th,e original acceptance l test,and I
- 3. )K The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is greater than or equal to - 7 1.190 and has not decreased more than 0.08 from the value observed during the previous test. .
m - -- %. . _
- c. At least once per 18 months by verifying that:
/
- 1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration,
- 2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, <L*d 4
3, X The battery charger will supply at least 3 amperes at > 125 volts for at least 4 hours.
- d. At least once per 18 months, during shutdown, by verifying that the tattery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours when the battery is subjected to a battery service test or the individual cell voltage does not decrease below 1.75 volts when the battery is subjected to the following equivalent load profile:
Order in Which Currrent Loads are Applied (amps)_ Duration 25 0 - 0.1 sec , 1 2 1 0.14- 2 hours l Sec FARLEY-UNIT 2 3/4 8-16
. 1 REFUELING OPERATIONS 3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER . .
LIMITING CONDITION FOR OPERATION i 3.9.14 The containment purge exhaust filter shall be OPERABLE and valve N1P13V293 closed. APPLICABILITY: During CORE ALTERATIONS and Fuel Movement inside containment with any containment purge isolation valve open.iSAR- l ACTION: With the containment purge exhaust filter inoperable either:
- 1. Immediately close the 48 inch containment purge isolation valves (CBV-HV-3196, 3197, 3198A and 31980) and the 18 inch containment mini purge isolation valves (CBV-HV-2866A, 2866B, 2867A and 2867B),
or
- 2. Cease all' CORE ALTERATIONS and fuel movement.
SURVEILLANCE REQUIREMENTS 4.9.14 The above required containment purge exhaust filter shall be i I demonstrated OPERABLE: 1
- a. At least once per 18 months or (1) after any' structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release that could have contaminated the charcoal adsorbers or HEPA filter in any ventilation zone communicating with the system by:
l' . l 9e;gep?f::r': :_.'.; i it!_'. '. 1 i;;di.;. 1 Amendment No.1 FARLEY-UNIT 2 3/4 9-16 --
e SPECIAL TEST EXCEPTIONS
; . 3/4.10.5 POSITION INDICATION SYSTEM - SHUTOOWN %.).
LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specification 3.1.3.3 may be suspended during the performance of individual full length (shutdowe and control) rod drop time measurements provided;
- a. Only one shutdown or control bank is withdrawn from the fully inserted position at a time, and The r sition indicator is OPERABLE during the withdrawal of the b.
rods. APPLICABILITY: MODES 3, 4 and 5 during performance of rod drop time measurements. ACTION: - With the position indication system inoperable or with more than one bank of-rods withdrawn, immediately open the reactor trip breakers.
-(
i-s SURVEILLANCE REQUIREMENTS 4.10.5 The above required rod position indication systems shall be determined to be OPERABLE within 24 hours prior to the start of and at least once per 24 hours thereafter during rod drop time measurements by verifying the demand position indication system and the rod position indication systems agree:
- a. Within 12 steps when the rods are stationary, and
- b. Within 24 steps during rod motion.
't app cabl duri g ei ti 1 e ibr ti of t
'
- Th requ'remen is
- les ovid ( K ma nta d pos' ion ndic ion sy tem f b nk s c ntr r
- or eq 1 to 0.95 and (2 only one ut wn with rawn from he ful ins ted osi ion t e t' e. ; O 3/4 10-5 FARLEY-UNIT 2
o . TABLE 4.11-1
)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Detectable Minimum Concentration Liquid Release Sampling Analysis Type of Activity (MDC) . Type Frequency Frequency Analysis (pCi/ml)a,g A. Batch Waste P P ~7 Releass Each Batch Each Betch Principa} Gama 5x10 e Emitters Tanks
-6 I-131 1x10 1x10
-5 P M Dissolved and One Batch /M Entrained Gases (Gamma emitters) 1x10
-5 P M H-3 b
Each Batch Composite -7 Gross Alpha 1x10 6 7 :: - :olf
-8 P Q Sr-89, Sr-90 5x10 b
Each Batch Composite
-6 Fa-55 1x10
-7 W Principa} Gamma 5x10 B. Continuous d D b Releases 'f Grab Sample Composite Emitters
-6 I-131 1x10
- 1. Steam -5 M Dissolved and 1x10 Generator M Blowdown Grab Sample Entrained Gases l
(Gamma Emitters)
-5 D M H-3 1x10 b
Grab Sample Composite
~7 Gross Alpha 1x10 )
-T : f6
-8 D Q Sr-89, St-90 5x10 b
Grab Sample Composite -6 Fe-55 1x10
?
-7 W PrincipleGgmma 5x10
- 2. Turbine P b
Grab Sample Composite Emitters -5 Builping H-3 1x10 Sump FARLEY-UNIT 2 3/4 11-2 _ - _ _ _ - _ _ _ _}}