Text

Forwards Draft STS Section 3.4, RCS, Per Meeting on 900507-10
	ML20055D963
Person / Time
Issue date:	06/25/1990
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	Hall W; NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &
References
	NUDOCS 9007100199
	Download: ML20055D963 (195)
	v • d • e

{{#Wiki_filter:- ' June ' 25,19901 Mr. Warren J. Hall, Manager Operations, Management and Support Services Division Nuclear Management and Resources Council 1776 Eye Street, Suite 300 Washington. DC 20006-2496

Dear Mr. Hall,

j Enclosed is the'first draft for the new STS section 3.4 Reactor' Coolant System. This draft incorporates,the.results of. our meeting with NUMARC and the Owners Groups on May 7-10, 1990. We understand that the'0wners Groups-will use this draft to prepare revised Bases for this-new STS section and will submit the Bases to the staff in-hard copy and on magnetic media in Wordperfect 5.1 by. August 3, 1990. Sincerely.. ORIGINAL. SIGEDRlE A. CALVO Jose A. Calvo, Chief Technical Specifications Branch Division of Operational Events Assessment. NRR

Enclosure:

) As stated cc: 'C. DeDeaux. CE06 Chairman DISTRI'BUTION: w/o Enclosure-J. Hinds. WOG Chairwoman TEMurley CHBerlinger. .C. Smyth B&WOG' Chairman FJMiraglia-1 PWBaranowsky. J. Jones, BWROG Chairman. -WTRussell. FGillespie; E. Lozito, VEPC0 CERossi 'JLieberman- 'B. Woods SCE JGPartlow ELJordan; K. Wilson, FPC DHCrutchfield. WGKennedyc J. l'owler.-SERI SAVarga_ MGMalsch: M. Bryan. TVA. GMHolahan-OTSB. Members J. Jones, GPC ACThadani ~ 0TSB r/f BKGrimes DOEA:r/f-JWRoel FJCongel JHConran'.

PDR w/ Enclosure i

(CentgalMMsjgaggQreg. l 1 i DOCUMENT NAME:- LTR TO'W.J. HAL TS :DOEA:NRR $:00EAiHRR OTS :00EAiHRRi C:0TSB:DOEA:NRR <Y[p)_ ~ NVGilles FMReinhart ' RMLobel -JACalvo /PE = 6 //7 /90 (//f/90 6 //7 /90 4 / r4790 7D' 9007100199 900625 N PDR REVGP ERONUMRC j PDC hk

RCS Pressure, 'iemperature, and Flow DNB-Limits-3.4.1 1 3.4-REACTORCOOLANTSYSTEM(RCS) 3.4.1 RCS Pressure. Temoerature and Flow DNB limits 4 LCO 3.4.1 RCS DNB parameters for loop pressure, hot leg temperature i and RCS total flow rate shall be within the limits specified-i below: a. With 4 Reactor Coolant (RC) pumps operating: RCS loop pressure shall-be 2 (2061.6] psi S RCS hot leg temperature shall be 1 [604.6 F, and l RCS total flow rate shall be 2-(139.7 E6] lbm/hr. b. With 3 RC pumps operating: RCS loop pressure shall be 2 (2057.2] psig RCS hot leg temperature shall be 5 (604.6]E, and 1 F_ RCS total flow rate shall be 2 (104.4 E6] lbm/hr. q I 1 APPLICABILITY: MODE 1. ......................N0TE----------------------------- i RCS loop pressure _ limit does not apply during: l a. A THERMAL POWER ramp-in excess of [5]% of RATED THERMAL POWER (RTP) per minute, or; b. A THERMAL POWER step in excess of [10]% of RTP. 3 t ACTIONS CONDITION REQVIRED ACTION-COMPLETION TIME l A. One or more RCS DNB A.1 Restore RCS DNB 2 hours. parameter (s) not parameter (s).to withinlimit(s). withinlimit(s). j 1 4 B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion 3 Time not met. 1 B&W STS 3.4-1 06/18/90 NI

a RCS Pressure, Temperature, and Flow DN8 Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-l SR 3.4.1.1 Verify RCS loop pressure 1 (2061.6] psig 12 hours with 4 RC pumps operating or 2 (2057.2) psig l with 3 RC pumps operating.. l l l SR 3.4.1.2 Verify RCS hot leg. temperature 1 (604.6]'F. - 12 hours. i l SR 3.4.1.3

NOTE------------------------

The provisions of SR 3.0.4 are not l applicable when changing reactor coolant i pump configurations while in. MODE 1. t -l Verify RCS total. flow 1 [139.7 E6] lbm/hr 12 hours i L with ( RC pumps operating or 1 [104.4 E6] lbm/hr with 3 RC pumps operating. SR 3.4.1.4 Demonstrate RCS total flow rate within limit-(18 months] l by measurement. l t CROSS-REFERENCES TITLE NUMBER Reactor Core Safety Limits 2.1.1 ? RCS Loops - MODES 1 and 2 3.4.4 w l B&W STS 3.4-2 06/18/90 4 e ! 4 n w n 4 -w....-.

RCS Minimum Temperature For Criticality 1 4 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) J 3.4.2 RCS Minimum Temperature For Criticality i LCO. 3.4.2 Each RCS loop average temperature (T,y) shall' be 1525'F. t in one or more RCS loops < 530'F. APPLICABILITY: MODE 1 with T**in one or more RCS loops < 530 F and K,,,21.0. MODE 2 with T,, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. T,in one or.more A.1 Restore T to 15 minutes RCS loops not within within liIn7t limit. QB A.2 Be in MODE 3. 30 minutes l-I l-I i I I 1 I B&W STS 3.4-3 06/18/90 C i

L RCS Minimui Temperature For Criticality-3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify T,, in each RCS loop 1525'F. Within 15 ( minutes prior to achieving criticality AtM 30 minutes l CROSS-REFERENCES \\ Illli NUMBER RCS Loops - Test Exceptions 3.4.17 4 e Yd i l 4 - B&W STS 3.4 4 06/18/90 i E. m. ...)

RCT P/T Limits 1 o 3.4.3 13. 4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temoerature (P/T) Limits LCO -3.4.3 The combination of RCS pressure, RCS temperature and RCS l heatup and cooldown rates shall be maintained within the limits specified in the PRESSURE' AND TEMPERATURE LIMITS REPORT. g APPLICABILITY: At all times. 9 ACTIONS CONDITION' REQUIRED ACTION COMPLETION TIME ..........N0TE----------- All Required Actions must be comploted whenever this Condition is

entered, l

A. Requirements of LC0 A.1 Restore parameters-30 minutes not met, to within limits. MD A.2 Determine RCS is 72 hours acceptable ' for continued operation. (continued) l B&W STS 3.4-5 06/18/90 o I s ..r .--~>-- ---u--

RCT P/T Limits 3.4.3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME i B. Required Actions and B.1 Be in MODE 3. 6 hoivs associated Completion Times not met. AND B.2 Be in MODE 5 with 36 hours l RCS pressure < [500] psig. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ...-NOTE--- only required-t l during RCS heatup and cooldown operations and in-service leak and hydrostatic testing. SR 3.4.3.1 Verify the combination of RCS' pressure and 30 minutes temperature and the heatup and-cooldown rates within limits. .y l l 4 b B&W STS 3.4-6 06/18/90 e -e- ~ =e ww,

H RCT P/T Limits 3.4.3 CROSS pfFERENCES TITLE NUMBER Reactor Core Safety Limits 2.1.1 l Reactor Coolant System Pressure Safety Limit 2.2.2 l 1 RCS Pressure,LTemperature, and Flow DNB Limits 3.4.1 j RCS Minimum Temperature for Criticality 3.4.2 Low Temperature Overpressurization Protection System 3.4.16 ( i i B&W STS 3,4 7 06/18/90

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCf, Loons - MODES 1 and 2 I LCO 3.4.4 [Two) RCS Loops shall be OPERABLE and in operation, with: a. 4 RC Pumps, or b. 3 RC Pumps and THERMAL POWER restricted to [79.9]% of RATED THERMAL POWER. l APPLICABILITY: MODES 1 and 2. -l ACTIONS' i CONDITION REQUIRED ACTION COMPLETION TIME-A. Required number of A.1 Be in MODE 3. 6 hours RCS loops not in operation. i l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-j SR 3.4.4.1 Verify required RCS loops and RC pumps 12 hours operating. 3 SR 3.4.4.2 Demonstrate steam generator tube integrity In accordance in accordance with the Steam Generator Tube with the Surveillance Program (Specification Steam .j 5.8.4.p.). Generator' Tube Surveil-lance Program (Specifi-cation 5.8.4.p.). ) j B&W STS. 3.4-8 06/18/90

l RCS Loops - MJDES I and 2 Q 3.4.4 CROSS-REFERENCES TITLE NUMBER f RCS Loops - Test Exceptions 3,4,17 1 b 1 l 1 l l l i 9 B&W STS 3,4 9 06/18/90 .c -v,,,, - ew .r-, ,,,a 9 --,-,,,.,,-,,.m,. ,,.,.,w--g ,-n... ... -.. +,

I RCS Leops. MODE 3 i 3.4.5 \\ 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Looos - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, with one RCS loop in I operation. ..........................N0TE---------- All Reactor Coolant (RC) pumps may be de-energized for 51 hour per 8-hour period, provided: i a. No o>erations are permitted that would cause reduction of tie RCS boron concentration, and b. Core outlet temperature is maintained at least (10)'F below saturation temperature. k APPLICABILITY: MODE 3. ACTIONS i CONDITION REQUIRED ACTION COMPLETION-TIME l A. One required RCS loop A.1 Restore required RCS 72 hours inoperable. loop to OPERABLE status. l_ B. Required Action and B.1 Be in MODE 4. 12 hours associated Completion Time of Condition A not met. 1 (continued) e 1 l B&W STS 3.4-10 06/18/90 1 4 ~.w._ ,_,t.- ..m

RCS Loops MODE 3 3.4.5 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. No RCS loop in C.1 Suspend all Immediately or ration, operations involving a reduction in RCS boron concentration. AND i C.2 Initiate action to Immediately restore one RCS loop to operation. i SURVEILLANCE REQUIREMENTS SURVEILLANCE. FREQUENCY i SR 3.4.5.1 Verify required number of RCS loops 12 hours operating. i SR 3.4.5.2 Verify correct breaker alignment and 7 days indicated power available to at least one RC pump per RCS loop. 1 CROSS-REFERENCES - None. B&W STS r.4 11 06/18/90 c ,,r.--....-e. _.r--

RCS Loops MODE 4 3.4.6 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.6 RCS Looos - HODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and Decay Heat Removal (DHR) loops shall be OPERABLE and at least one loop shall be in operation. ...........................N0TE-

~~-

1. All RC pumps and DHR pumps may be de energized for s I hour per 8 hour period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration, and 3

b. Core outlet tempereture is maintained-at least (10]'F e

below saturation temperature. 2. No RC pump shall be started with one or more RCS cold leg temperatures 1 [ J'F unless the secondary-side water temperature of each steam generator is < [ J'F l above eac1 of the RCS cold leg temperatures. i APPLICABILITY: MODE 4. i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Initiate action to 15 minutes inoperable, return a second loop to OPERABLE status. NiQ Two DHR loops inoperable. (continued) B&W STS 3.4 12 06/18/90 i w

I RCS Loops - MODE 4 l 3.4.6 ) ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME l l B. One DHR loop B.1 Restore required I hour i inoperable. loop to OPERABLE status. l AND E Two RCS loops inoperable. B.2 Be in MODE 5. 25 hours l-C. No RCS or DHR loop in C.1 Suspend all Imediately operation, operations involving a reduction in RCS boron concentration. i C.2 Initiate action to Imediately l restore one loop to operation. 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify steam generator secondary side water 12 hours level 1 [ ]% for required OPERABLE RCS loops. 1 SR 3.4.6.2 Verify at least one DHR or RCS loop 12 hours operating, r (continued) B&W STS 3.4 13 06/18/90 .-. e ~. _

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMEN1S (continued) SURVEILLANCE FREQUENCY l SR 3.4.6.3 Verify correct breaker alignment and 7 days indicated power available to the required pump that is not in operation. CROSS-REFERENCES TITLE NUMBER ECCS Trains - Shutdown 3.5.3 i Low Temperature Overpressurization Protections System 3.4.16 i 6 l B&W STS 3.4-14 06/18/90 l j.

4 RCS Loops o MODE 5, Loops FillCd a 3.4.7 3.A REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loons - MODE 5. Looer Filled LCO 3.4.7 One RCS loops or one Decay Heat Removal (DHR) loop shall be OPERABLE and in operation, and either: a. One additional DHR loop shall be OPERABLE, or b. The secondary side water level of each Steam Generator (SG) shall be 2 ( ]%. ..........................N0TES 1. The DHR pump of the DHR loop in operation may be de-energized for 1 1 hour per 8-hour period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration, and

b. Core outlet temperature is maintained at least 10'F below saturation temperature.

2. One DHR loop may be inoperable for up to 2 hours for surveillance testing provided that the other DHR loop is OPERABLE and in operation. 3. No RC pump shall be started with one or more RCS cold leg temperatures s [ ]'F unless the. secondary-side water temperature of each SG is s ( J'F above each of. the RCS cold leg temperatures. APPLICABILITY: MODE 5 B&W STS 3.4 15 06/18/90 --a, w

) RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS i CONDITION REQUIRED ACTION COMPLETION TIME l A. Only one loop A.1 Initiate action to 15 minutes OPERABLE. restore a second loop to OPERABLE 88Q status. Less than the E required secondary side water level in A.2 Intiate action to 15 minutes any SG. restore SG secondary side water levels to ) within limits. B. No DHR or RCS loop B.1 Suspend all Immediately OPERABLE. operations involving a reduction in RCS E boron concentratior.. No DHR or RCS loop in ANQ operation. B.2 Initiate action to Immediately restore one DHR or RCS loop to OPERABLE status and operation. j SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify SG secondary side water levels 1 12 hours [ ]%. 4-SR 3.4.7.2 Verify at least one DHR or RCS loop 12 hours operating. (continued). B&W STS 3.4-16 06/18/90 \\

RCS Loops - MODE 5, Loops Filled 3.4.7 l SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY j SR 3.4.7.3 Verify correct breaker alignment and -- NOTE---- indicated )ower availabile, to the required Only required DHR loop t1at is not in operation. if secondary side water s [ ]% in any SG. 7 days I CROSS REFERENCES TITLE NUMBER Low Temperature Overpressurization Protection 3.4.16 4 L i B&W STS 3.4-17 06/18/90 --,-,.e--~ ---.-_.,,.--~..r-w.-

RCS Loops o MODE 5, Loops Not Filled i 3.4.8 3.4 REACTGR COOLANT SYSTEM (RCS) ~ 3.4.8 RCS Looos. MODE 5. Looos Not Filled i LCO 3.4.8 Two Decay Heat Removal (DHR) loops shall be OPERABLE and at least one DHR loop shall be in operation. ..........................N0TES------ ---~~---.------------- One DHR loop may be inoperable for u) to 2 hours for surveillance testing provided that tie other DHR loop is OPERABLE and in operation. APPLICABILITY: MODE 5 with RCS loops not filled, l ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME ) A. One DHR loop A.1 Initiato actions to 15 minutes inoperable, restore DHR loop to OPERABLE status. B. No DHR loop OPERABLE. B.1 Suspend all Immediately operations invoving QB a reduction in reactor coolant i No DHR loop in boron cov entration, operation. AtlQ B.2 Initiate action to Immediately restore one DHR loop to OPERABLE status and operation. i i 1 B&W STS 3.4-18 06/18/90. m r.--.-. -e y _e

r RCS Loops MODE 5, Loops Not filled 3.4.8 SURVEILLANCE REQUIREMENTS i SURVEILLANCE FREQUENCY i SR 3.4.8.1 Verify at least one OHR loop operating. 12 hours SR 3.4.8.2 Verify correct breaker alignment and 7 days indicated power available to the required OHR pump that is not in operation. i l i CROSS-REFERENCES - None. i { l i i B&W STS 3.4 19 06/18/90 .-.-.-,e- ., - -. - - -, - - - - - = -

l Pressurizer Water Level 3.4.9 l 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Erg 3surizer Water Level LCO 3.4.9 Pressurizer water level shall be 1 ( ) inches. i APPLICABILITY: MODES 1, 2 and 3. MODE 4 with RCS temperature 1 (275]'F. i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water A.1 Be in MODE 3 with 6 hours level not within control rod drive limit. trip breakers open.

A 12 hours

't. 2 Be in MODE 4 with RCS temperature i (275)'F. SURVEILLANCE REQUIREMENTS l SURVEILLANCE FR QUENCY SR 3.4.9.1 Verify ' pressurizer water level I ( ) inches. 12 hours L CROSS-REFERENCES - None. l l B&W STS 3.4-20 06/18/90 e ,-e m. w

i Pressurizer Hea+.ers l F o 3.o.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Heaters l LCO 3.4.10 A minimum of (126] kw of aressurizer heaters shall be capable of being powered ay an emergency power supply. APPLICABILITY: MODES 1, 2, arid 3 l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME t A. Capacity of A.1 Restore pressurizer 72 hours' [ pressurizer heaters heater capability. capable of being powered by emergency power supply less than limit, i B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours c I B&W STS 3.4-21 06/18/90 c,- .-.,y,-,,.

Pressurizer Heaters 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify 1 (126] kw of pressurizer heaters kre (18 months) capable of being powered by emergency power supply. (SR 3.4.10.2 Demonstrate the emergency power supply for (18 months) ) pressurizer heaters is OPERABLE. CROSS REFERENCES - None. 1 i 3 B&W STS 3.4 22 06/18/90 l \\

Pressurizer Safety Valves 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Safety Valves LCO 3.4.11 Two pressurizer safety valves shall be OPERABLE with lift settings 2 (2475) psig and 1 (2525).psig. .........................N0TE

-----~~----------------

LCO 3.0.4 and SR 3.0.4 are not applicable for entry into MODES 3 and 4 for the purpose of setting the pressurizer-cede safety valves under ambient (hot)llowing entry into conditions. This exception is allowed for (36] hours fo MODE 3 provided a preliminary cold setting was made prior to heatup. APPLICABILITY: MODES 1, 2, and 3 MODE 4 with any RCS cold leg temperature > [275)'F. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer A.1 Restore valve to 15 minutes: safety valve OPERABLE status, inoperable. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. 8tiQ B.2 Be in MODE 4 with 12 hours all RCS cold leg i temperatures s (275)'F. B&W STS 3.4-23 06/18/90 4 e

J Pressurizer Safety Valves 3.4.11 SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY SR 3.4.11.1 Demonsteate each pressurizer safety valve In accordance OPERABLE in accordance with the Inservice with the Test.ing Program. Inservice Testing R

Program, t

l' CROSS REFERENCES - None. a I I i B&W STS 3.4 24 06/18/90 e l

Pressurizer PORVs 3.4.12 3.4 REACTORCOOLANTSYSTEM(RCS) i 3.4.12 Pressurizer Power Operated Relief Valves =(PORVs) ) LCO 3 A.if One PORV and associated block valve shall be OPERABLE. I APPLICABILITY: MODES 1, 2, AND 3. ...........N0TE------------- LCO 3.0.4 is not applicable. l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1 1 A. PORV inoperable. A.1 Restore PORV to I hour OPERABLE status. M A.2 Close the block I hour valve. B. Block valve B.1 Restore block valve I hour inoperable. to OPERABLE status. l E B.2.1 Close block valve. I hour M B.2.2 Remove power from I hour block valve. E (continued) B&W STS 3.4-25 06/18/90 -,,. ~. .a e

Pressurizer PORVs 1 3.4.12 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3.1 Close PORV. I hour l AND i B.3.2 Remove power from I hour PORV solenoid valve. C. Required Actions and C.1 Be in MODE 3. 6 hours associated Completion Times not met. AHQ i C.2 Be in MODE 4. 12 hours J SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY SR 3.4.12.1 --- ----- ------ NOTE -- ---- -------- Surveillance 801 required with block valve closed in accordance with the Required Actions of this LCO. Perform one complete cycle of the block .92 days l valve. SR 3.4.12.2 Perform CHANNEL CALIBRATION for PORV.. (18 months) SR 3.4.12.3 Perform one complete cycle of the FORV. (18 months) (continued) B&W STS 3.4 26 06/18/90 j . ~.,._

Pressurizer PORVs 3.4.12 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY [SR 3.4.12.4 Demonstrate emergency power supply for PORV (18 months) ) and block valve OPERABLE. CROSS REFERENCES - None. i B&W STS 3.4-27 06/18/90 l

r LTOP Syste] 3.4.13 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.13 i Temoerature Overoressurization Protection (LTOP) System LCO 3.4.13 A LTOP System shall be OPERABLE with a maximum of (one) High PressureInjection(HPI)pumpOPERABLE,and: a. Pressurizer level s ( ) inches and an OPERABLE power operated relief valve (PORV) with a setpoint of s(525]psig,or b. The RCS depressurized with an open RCS vent of 2 ( ) square inches. APPLICABILITY: MODE 4 with RCS temperature less than or equal to (275]'F, MODE 5, MODE 6 with the reactor vessel head on. .............N0TE---- LCO 3.0.4 is not applicable. l l ACTIONS i CONDITION REQUIRED ACTION COMPLETION TIME l l A. More than (one) HPI A.1 Initiate action to Immediately l pump OPERABLE. ensure a waximum of [one) liPi pump OPERABL(, l (continued) l B&W STS 3.4-28 06/18/90 P 4 e-e rm-- -e er ,,e -r , ~ - - e--

i I LTOP System 3.4.13 ACTIONS (continued)- i CONDITION REQUIRED ACTION COMPLETION TIME l B. LTOP system B.1 Restore LTOP System I hour inoperable. to OPERABLE status. E ] B.2 Deactivate each I hour makeup pump. E B.3 Deactivate each HPI 1 hour valve in the closed i position. / C. Required Action and C.1 Depressurize RCS to 12 hours i associated Completion atmospheric aressure Time not met, and establisi RCS vent of 2 [ ] square inches. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify a maximum of (one) HPI pump OPERABLE. Within 15 l minutes prior to decreasing RCS temperature to 1 (275)*F MD 12 hours (continued) B&W STS 3.4-29 06/18/90 -,n-m - e. e

LTOP System 3.4.13 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.4.13.2 Verify required RCS vents open: a. For unlocked open vent valves, and 12 hours b. For locked open vent valves 31 days SR 3.4.13.3 Verify pressurizer level 5 [ ] inches. 12 hours SR 3.4.'3.4 Verify PORV block valve open. 12 hours i SR 3.4.13.4 NOTE-------- SR 3.0.4 is not applicable. Perform a CHANNEL FUNCTIONAL TEST, excluding 31 days valve operation, for PORV.~ SR 3.4.13.6 Perform CHANNEL CAllBRATION for PORV. [1B months) i CROSS-REFERENCES TITLE NUMBER RCS Pressure and Temperature Limits 3.4.3 B&W STS 3.4-30 06/18/90

c RCS Operational LEAKAGE l 3.4.14 3.4 REACTOR COOLANT SYSTEh (RCS) f 3.4.14 RCS Ooerational LEAKAGE LCO 3.4.14 RCS Operational LEAKAGE shall be limited to: a. No Pressure Boundary LEAKAGE; b. I gpm Unidentified LEAKAGE: c. 10 gpm Identified LEAKAGE from the RCS. d. I gpm total primary-to-secondary LEAKAGE through all steam generators; and e. (720] gallons per day primary to secondary LEAKAGE through any one steam generator. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 3 A. RCS leakage not A.1 Reduce leakage to 4 hours within limits for within limit. reasons other than Pressure Boundary LEAKAGE. B. Requirtd Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AE L not met. B.2 Be in MODE 5. 36 hours 0.B l Pressure Boundary LEAKAGE exists. t B&W STS 3.4 31 06/18/90

RCS Operational LEAKAGE I 3.4.14 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l l SR 3.4.14.1 ---N0TE...--...--.-.---.--. -..--NOTE---. SR 3.0.4 is not applicable for entry into Only required MODES 3 and 4. during steady state opera-tion. Perform a RCS water inventory balance. 72 hours CROSS REFERENCES TITLE NUMBER RCS Pressure Isolation Valve Leakage 3.4.15 RCS Leakage Detection Instrumentation 3.4.16 a ? t B&W STS 3.4-32 06/18/90 4 e .... -. + -

.w.

,e .-...--w- ,,..wo.,, , ~. -.... ,----,..e

o RCS P!V Leakage 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Pressure Isolation Valve (PlV) Leakaae LCO 3.4.15 The leakage from each RCS PIV shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure 2 ( ) and s ( ) psig. APPLICABILITY: MODES 1, 2, 3 and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage for one or A.1 Restore RCS PIV 4 hours more RCS PIV not leakage rate to within limit. within limit. QB (continued) t l l l l l B&W STS 3.4-33 06/18/90- _,,,,i e e +y,

RCS PIV Leakage 3.4.15 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) --NOTE----------- 4 hours Each valve used to satisfy Required Action A.2.1 or A.2.2 must have been demonstrated to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary. A.2.1 Isolate the high pressure portion of the affected system 72 hours from the low pressure portion by use of one closed manual, deactivated automatic or check valve. MQ A.2.2 Isolate the high pressure portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic or check valve. B. Required Action and B.I Be in MODE 3. 6 hours associated Completion Time not met. MQ p B.2 Be in MODE 5. 36 hours B&W STS 3.4-34 06/18/90 f ---m-. +,.._ _

RCS PIV Leakage 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 --..---......---NOTE---- SR 3.0.4 is not applicable for entry into MODES 3 and 4 for the purpose of testing the isolation valves. Verify leakage from each PIV limited to 0.5 (18 months) gpm per nominal inch of. valve size up(to a maximum of 5 gpm at a RCS pressure 2 ) AND and 1 ( ) psig. Prior to entering MODE 2 whenever the plant has been in MODE 5 for 7 days or more, and if leakage testing has not been performed in the previous 9 months AND Within 24 hours following valve actuation due to automatic l or manual action, or flow through the valve B&W STS 3.4 35 06/18/90 ~ - - -. -b -- - .e -e- ~ * ~

i I RCS P!V Leakage 3.4.15 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY (SP. 3.4.15.2 Verify Decay Heat Removal (DHR) System auto-(18 monthsj ] closure interlock prevents the valves from being opened with a simulated or actual RCS pressure signal 1 (284) psig. (SR 3.4.14.3 Verify DHR System autoclosure interlock (18 montns) ) cauced the valves to close automatically with a simulated or actual RCS pressure signa's 2 (284) psig, i Mmf CROSS REFERENCES TITLE NUMBER RCS Loops - MODE 4 3.4.5 RCS Operational Leakage 3.4.14 s Core Flood Tanks 3.5.1 ECCS Trains - Operating 3.5.2 Containment Isolation Valves 3.6.3 i B&W STS 3.4-36 05/18/90 e ..-..s

E RCS Leakage Detection-Instrumentation 3.4.16 4 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.16 RCS Leakaae Detection Instrumentation' i LCO 3.4.16 The following RCS leakage detection. instrumentation shall be OPERABLE: a. One containment sump monitor, and' b. One containment atmosphere radicactivity monitor, l foaseous or particulate). ( APPLICABILITY: MODES 1, 2, 3 and 4. j I ACTIONS CONDITION REQUIRED ACTION. COMPLETION TIME A. Required containment -A.1" Perform-SR 3.4.14.1. - Once per 24 sump monitor hours inoperable. Ag A.2- -Restore monitor to 30 days OPERABLE status, i (continued) t i j B&W STS 3.4-37 06/'.8/90 ' ) f

4 RCS Leakage' Detection Instrumentation 3.4.16 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1.1 .Take and analyze Once per 24 atmosphere radio-grab samples of the hours activity monitor-containment inoperable, atmosphere. QB I B.1.2 Perform SR 3.4.14.1. Once per 24 hours ABD J .B.2 Restore containment 30 days t atmosphere rtiio-activity monitor to OPERABLE status. C. Required Actions and C.1 Be in' MODE 3. 6 hours associated Completion Times not met. ANJ C.2 Be in MODE 5.- 36 hours D. Both required D.1 Enter LCO 3.0.3. Immediately monitors inoperable. 5 I 1 i B&W STS 3.4-38 06/18/90 t ...:-~J--..- .,J....., -_.-,.-- l

RCS Leakage Detection Instrumentation 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Perform a CHANNEL CHECK of required 12 hours containment atmosphere radioactivity monitor. SR 3.4.16.2 Perform a CHANNEL FUNCTIONAL TEST of -31 days raquired containment atmosphere radio ' activity monitor. SR 3.4.16.3 Perform a CHANNEL CALIBRATION of required (18 months) containment atmosphere radio-activity monitor. SR 3.4.16.4 Perform a CHANNEL CALIBRATION of containment (18 months] sump level monitor. i k CROSS-REFERENCES TITLk NUMBER ~ RCS Operational Leakage 3.4.14 .) a B&W STS 3,4-39 06/18/90 g i

RCS Specific Activity 3.4.17 3.4 REACTOR COOLANT SYSTEM'(RCS) 3.4.17 RCS Soecific Activity LCO 3.4.17 The specific-activity of the primary coolant shall be limited to: a. A gross specific activity 1 100/t and b. A DOSE EQUIVALENT I-131 (del-131) specific activity-1 1.0 yCi/gm, and APPLICABILITY: MODES 1 and 2, MCDE 3 with T,y, 1 500'F. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross specific _ A.1 Determine' DOSE.- 4 hours activity of the EQUIVALENT I-131. primary coolant not within limit, eg A.2 Be in MODE 3 with 6 hours - T,y, < 500'F. (continued) I B&W STS '3.4-40 06/18/90 6

i RCS Specific Activity I ~3.4.17 ACTIONS (contin 6cd) CONDITION REQUIRED ACTION toMPLETION TIME 1 1 ~ B. DOSE EQUIVALENT I-131 B.1-Demonstrate DOSE Once per 4 > 1.0 #Ci/gm. EQUIVALENT l-131 hours within the acceptable region of Figure 3.4.17-1. AND. B.2 Restore DOSE 48 hours ) EQUIVALENT l-131.to j within limit. 1 C. Required Actions and C.1 Be in MODE e with 6 hours. associated Completion -T* < 500 F. Times of Condition B not met. QB DOSE EQUIVALENT I-131 in unacceptable region ofcFigure 3.4.17-1. i I .B&W STS 3.4-41 06/18/90

RCS Specific Activity 3.4.17 SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY j i SR 3.4.17.1 Demonstrate primary coolant gross specific 72 hours activity 5100/E #Ci/g. SR 3.4.17.2

NOTES----------------

NOTE----

1. SR 3.0.4 is not applicable. Only required i in MODE 1. 2. Sample after a minimum of 2 EFPD and 20 days of MODE 1: operation have elapsed since the reactor was last subcritical for 1 48 hours. Determine i by radiochemical analysis. 184 days 4 SR 3.4.17.3 Demonstrate primary coolant DOSE' EQUIVALENT 14 days I-131 specific activity 51.0 pCi/g. AtlQ Between 2 and j 6= hours after THERMAL POWER change of 2 j 15% of RTP within a 1-hour period i CROSS-REFERENCES - None. i 4 S&W STS 3.4-42 06/18/90 4 l t

4 RCS Specific ActivityL' 3.4.17; Figure 3.4.17-1 (Page 1 of 1) DOSE EQUIVALENT I-131 Primary Coolant Activity Versus. Percent of RATED THERMAL POWER With Primary Coolant Specific Activity > 1.0 pCi/gm DOSE EQVIVALENT I-131. '( i t l -1 .1 'B&W STS 3.4-43 06/18/90

i RCS Pressure, Temperature, and Flow DNB Limits-3.4.1 3.4 REACTOR' COOLANT SYSTEM (RCS) - 3.4.1 RCS Pressure. Temoerature and Flow DNB Limits 1 i 1 -LC0 3.4.1 RCS-DNB-parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the ' limits specified below: 1 a. Pressurizer pressure 2.[2025]-psia and s (2275] psia,- b. RCS cold leg temperature- (T ): 2 (535]'F and s (558]*F for,< (70]% of RTP, or '1 2 (544] F and s (558] F for 2 (70]% of RTP, and c. RCS total flow rate 2 (148 E6] Libm/hr and s (177.6 E6] lbm/hr. APPLICABILITY: MODE 1. ..........................-N0TE----------------------------- Pressurizer pressure limit does not apply during: a. A THERMAL POWER ramp in excess of (5]% of RATED THERMAL POWER (RTP)perminute,or; b. A THERMAL POWER step in' excess of [10]%'of RTP. ACTIONS CONDITION REQUIRED ACTION: COMPLETION TIME A. Pressurizer pressure A.1 Restore parameter to-2 hours. or RCS flow not within limit. within limit. 1 B. Required Action and B.1 Be in MODE 2. .6 hours 4 associated: Completion-Time of Condition A not met. (continued) CE0G STS 3.4-1 06/18/90 0 1 -~n, u a -.-a, .ne, .ene,,, w-. ~ ,,e.-,so'w e, e.e. w s.

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 . ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME' C. RCS cold leg C.1 Restore cold leg 2 hours j tem >erature not temperrtre to_ i witiin limit, within I D. Required Action and D.1 Reduce THERMAL' POWER 6 hours associated Completion to < (30]% of RTP. Time of Condition C not met. H i s SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressure'2_(2025] psia and s [2275] 12 hours-psia.. SR

3. 4.1. 2 -

Verify RCS cold leg temperature 2 (535]'F 12 hours i and s (558]'F for < [70]% of RTP or 2 [544] F and s [558] F for.2 [70]% of RTP, i ....................N0TE------------------- This surveillance requirement only applies in MODE 1. SR. 3.4.1.3 Verify RCS total flow rate 2 (148 E6] lbm/hr 12 hours and s (177.6 E6] lbm/hr.

== (continued)- i CE0G STS 3.4-2 06/18/90'

RCS Pressure, Temperature,' and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY ....................N0TE------------------- i SR 3.0.4 is not applicable. i SR 3.4.1.4 Determine RCS total flow rate 2 (148 E6] (10 months) lbm/hr and.s (177.6 E6]-lbm/hr measurement. CROSS-REFER'ENCES ~ TITLE NUMBER . Reactor Core Safety Limits 2.2.1 RCS Loops >- MODES 1 and 2 3.4.4 1 A CEOG STS 3.4-3 '06/18/90 i I t U

. RCS Minimum Temperature for Criticality 2.4.2 ~ I 3.4 REACTOR COOLANT SYSTEM'(RCS) 3.4.2 RCS Minimum Temoerature for Criticality i LCO 3.4.2 Each RCS loop average temperature (T,y) shall be 2 [520] F. ] l 1 APPLICABILITY: MODE 1 with T, in one or more RCS loops < [535]'F, MODE 2 with T,, in one or more RCS loops < [535]'F, K,, 2 1.0. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME [T in one or more A.1 Restore [T ] to 15 minutes RC$9]00psnotwithin withinliml*t. A. limit. DB A.2 Bo in MODE 3. 30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS [T,y] in each loop 2 [520] F. Within 15. minutes prior to achieving criticality. ) i b 30 minutes CE0G STS 3.4-4 06/18/90 m---a--a e=~w-- e-- -%a-. a w-

e.

s

---ewe e s w s-- w- ---ew,*- ,'N w s a +fe+'+-

um

_--_,eA-ea-- = - -3ww-

..~ RCS Minimum Temperature for Criticality 3.4.2 CROSS REFERENCES TITLE l$ UMBER Special. Test Exception - RCS Loops

3. 4 ~.17 1

'? k i i L f i 1 j i e CE0G.Si3 3.4-5 06/18/90-1

^

.. -.. ~..

RCS P/T Limits 4 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/Tf limits LCO 3.4.3 The combination of RCS pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within the limits specified in the PRESSURE AND TEMPERATURE LIMITS REPORT. APPLICABILITY: At all-times. ACTIONS CONDITION-REQUIRED ACTION COMPLETION TIME ...........N0TE---------- ? All Required Actions must 1 be completed whenever this Condition isL entered. A. Requirements of the A.1 Restore parameter (s) 30 minutes LCO not met. to within limits. 68Q A.2-Determine RCS is 72 hours. acceptable for ) continued operation. l B. -Required Action and B.1 Be in-MODE 3. 6 hours associated Completion-Time not met, eHQ B.2 Be in MODE 5 with 36 hours RCS pressure < [500) psi 9 9 l- .CE0G STS .3.4-6 06/18/90 l l.

RCS P/T Limits J 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the combination of RCS pressure and

NOTE-----

temperature and the heatup and cooldown Only required rates within limits, during RCS heatup and cooldown -operations and. inservice leak and hydrostatic testing. 30 minutes CROSS-REFERENCES TITLE NUMBER Reactor Core Safety _ Limits 2.1.1 Reactor Coolant System Pressure Safety Limit 2.2.l' RCS Pressure, Temperature, and Flow DNB Limits 3,4.1 RCS Minimum Temperature for Cri+1cality 3.4.2 Low Temperature Overpressure Protection System: 3.4.12 CEOG STS 3.4-7 06/18/90 l lo

=! RCS Loops . MODES 1 and 2 3.4.4 3.4 . REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loon - MODES 1 and 2 LCO 3.4.4 Two RCS loops shall be OPERABLE and in operation. APPLICABILITY:- MODES 1 and 2. ACTIONS CONDITION' REQUIRED ACTION COMPLETION TIME -j A. One or more RCS loops A.1: Be in MODE 3. 6 hours i not in operation. i i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY. SR 3.4.4.1 Verify-each RCS loop in operation. 12 hours 1 SR 3.4.4.2 Demonstrate steam generator tube integrity In'accordance in accordance with the Steam Generator Tube with Steam Surveillance Program (Specification Generator 5.8.4.p). Tube Surveillance Program (Specifi-cation-5.8.4.p) J CEOG STS 3.4-8 06/18/90

.. _ _. _ _ _ _ _ _ _ _ ~. _ _ RCS Loops - MODES 1 and 2 3.4.4 CROSS-REFERENCES TITLE NUMBER l-RCS Loops - Test Exception' 3.4.17 i i l i s 1 i i e t 3-i i J 4 4 i.I -CE0G STS 3.4-9 06/18/90 E b ,no ,s +s ,--+~--n- ,,wi, ,,.,,~,..Jr .n c w.- - -, -...., -~

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loons - MODE 3 LCO' 3.4.5 [Two) RCS loops shall. be OPERABLE and one RCS loop shall be in operation. .........................N0TE------------------------------ All'RCPs may be de-energized for up to I hour per 8-hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration, and b. Core ottlet temperature is maintained at least 10*F below saturation temperature. 1 APPLICABILITY: M00E:3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop-A.1 Restore required RCS - 72 hours inoperable. loop to OPERABLE status. B. Required Action and B.1 Be in MODE 4. [12] hours associated Completion Time of Condition A L not met. L L (continued) L o I t l-CE0G STS 3.4-10 06/18/90 e-e c. .ww,+... -..m m.'+ e-w, w.-e+e,-a-+ww ,.e,

we er--+,-

w-q w,- w.

y RCS Loops -. MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify at least one RCS loop operating. 12 hours-- SR 3.4.5.2 Verify secondary-side water level of both 12 hours steam generators 2 (25]%. ~ t SR 3.4.5.3 Verify correct breaker alignment and 7 days . indicated power available to at least one RCP per RCS loop. CROSS-REFERENCES - None. f f 9 l CE0G STS 3.4-11 06/18/90-I a e

RCS Loops.' MODE 4 A 3.4.6 3.4' REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loons. MODE 4 LCO 3.4.6 Two loops / trains consisting of any combination of RCS loops and Shutdown Cooling (SDC) trains shall be OPERABLE and at least one loop / train shall be in operation. ........................--N0TE----------------------------- 1. All RCPs and.SDC pumps may be'de-energized for up to I hour per 8-hour period provided: a. No operations are permitted that would cause reduction of,the RCS-boron. concentration, and b. Core outlet temperature is maintained at least,10'F below saturation temperature.. 2. No RCP shall be started with any RCS cold leg temperatures s (285]'F unless: a. .The pressurizer water level-is < [35%), or b. The secondary water temperature of each steam generator is < [100] F above each of the RCS cold leg temperatures.- APPLICABILITY: MODE 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME-A. One RCS loop A.1 Initiate action to 15 minutes inoperable return a second loop / train to AHD OPERABLE status.. Two'SDC trains inoperable. (continued) CEOG STS 3.4-12 06/18/90-F

RCS Loops - MODE 4 3.4.6 ACTIONS (continued) CONDITION REQUIRED ACTION. COMPLETION TIME B. One SDC train B.1 Restore a second I hour inoperable. loop / train to OPERABLE status. M QB Two RCS loops - inoperable. B.2 Be in MODE 5. 25 hours. C. No RCS loops or SDC C.1 Suspend all Immediately trains in operation.. operations Involving reduction in RCS boron concentration. E C.2 Initiate action to Immediately restore one-loop / train to operation.. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify secondary-side water level of 12 hours required steam generator (s) 2 [25]%. SR 3.4.6.2 Verify at least one RCS loop or SDC train 12 hours operating. SR 3.4.6.3 Verify correct breaker alignment and 7 days indicated power available to the required, pump not in operation. CE0G STS 3.4-13 06/18/90

RCS Loops - MODE 4 3.4~.6 ~ CROSS-REFERENCES TITLE NUMBER ECCS Trains - Shutdown 3.5.3 l Low Temperature Overpressure Protection System 3.4.12 l 1 l 1 I CEOG STS 3.4-14 06/18/90-4 I.'

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Reactor Coolant Looos and Circulation - MODE 5. Looos Filled LCO 3.4.7 One RCS loop or one SDC train shall be OPERABLE and in operation, and either: a. One additional SDC train shall be OPERABLE, or ~ - b. The secondary side water. level of each Steam Generator (SG) shall be > (25% wide range]. ...........................N0TE------------------------- 1. All Reactor Coolant Pumps (RCPs) and SDC pumps may be de-energized for s I hour per 8-hour period provided: i

a. No operations are permitted that would causa reduction of the RCS boron concentration, and-s

b. Core outlet temperature is maintained at least 10 F below saturation temperature.

2. One SDC loop may be-irloperable for up to 2 hours for surveillance testing provided that the other SOC loop is OPERABLE and in operation. 3. No RCP shall be started with one or more-of the RCS cold leg temperatures 1 [285]'F unless:.

a. The pressurize water level,is < [35]%, or 4

b. The secondary water temperature ot each SG is

< [100]*F above each-of the RCS cold leg temperatures. APPLICABILITY: MODE 5 with RCS loops filled.. c x Y I CEOG STS 3.4-15 06/11/90 + \\

RCS Loops - MODE 5,-Loops Filled. 3.4.7 ACTIONS ~ CONDITION REQ IRED ACTION COMPLETION TIME A. Only one loop / train -A.1 Initiate action to 15 minutes OPERABLE. return a second i loop / train to 88Q-OPERABLE status. Less than the QB ' required secondary. side water level in any SG. A.2 Initiate action-to-15 minutes restore the requiredt SG sc.ondary side water level to-within limits. B. No SDC train or RCS B.1 -Suspend all-Immediately loop OPERABLE. operations involving reduction in RCS 4 QB boron concentration. J No SDC train or RCS AN.D loop in operation. B.2 Ihitiateactionto-Immediately restore one SDO train or RCS loop to OPERABLE status and operation. 1 -1 i i a ,h .i CEOG STS 3.4-16 06/11/SO-l ).. a' -.,-,.-,L.. ..:-.~.. .w. .. s,. s

s' RCS Loops - MODE 5, Loops Filled 3.4.7 SVRVEILLANCE REQUIREMENTS SURVEILLANCE ' FREQUENCY SR 3.4.7.1 Verify SG secondary-side water levels

NOTE-----

2 (25]%. Only required if only-one train is OPERABLE. 12 hours: SR 3.4.7.2 Verify one SDC train or RCS loop operating. 12 hours l SR 3.4.7.3 Verify correct breaker alignment and

NOTE----

indicated power available to' the required _0nly required SDC train which is not in op; ration, if secondary-side water l L level is s (25% wide range] in any.- r SG-i 7 days' i e ?

I CROSS-REFERENCES - None.

l= l \\ v t 4 l tr -i . /; o ' CEOG STS 3.4-17 f, 06/11/90' i j ' 4, I ' (. t f j J, t i s { l' j, >l , ~ ' ~ ' ' f. l[ __ _ _,. _ _.__.______,a___,J'

m -j, l RCS Loops - MODE 5,: Loops Not F111Gd-3.4.8 3;4 REACTORCOOLANTSYSTEM(RCS) l i 3.4.8 RCS Loops - MODF, 5. Looos Not Filled 4 l LCO 3.4.8 Two Shutdown Cooling (SDC) trains shall be OPERABLE, and at i least one train shall be in operation. ..........................N0TES------------------------------ One SDC train may be inoperable for m to 2 hours for surveillance testing, provided the otler SDC train is OPERABLE and in operation.

i APPLICABILITY

MODE 5 with RCS loops not filled. i ACTIONS CONDITION REQUIRED ACTION COMPLETION. TIME A, One SDC train A.1 Initiate action to. 15 minutes inoperable. - restore train to OPERABLE status. B. No SDC train 8.1 Suspend all Imediately OPERABLE. ' operations involving, reduction in RCS QB boron concentration. ~No SDC train in 6NQ ~; operation. l B.2 Initiate action to' .Imediately restore one SDC-- . train to OPERABLE status and operation. l. l F -1 l( j '~ CE0G STS 3.4 1C 06/18/90-p

l RCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY l SR 3.4.8.1 Verify at least one SDC train operating. 12 hours i SR_ 3.4.8.2 Verify correct bretker alignment and 7 days indicated power available to the required SDC train that is not in operation. l CROSS-REFERENCES - None. 4 0 J h b f CE0G STS 3.4-19 06/18/90 -w w-o- e w -me-, v

.. - ~. Pressurizer 3.4.9 3.4 REACTOR-COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with: a. Pressurizer water [ lev >l < 35]%, and b. At least two groups of pressurizer heaters OPERABLE with the capacity of each group being at least [150] kW and capable of being powered from an emergency power supply. APPLICABILIlY: MODES-1, 2, and 3. ACTIONS CONDIT1'ON REQUIRED ACTION COMPLETION' TIME A.. Pressurizer water A.1 Be in MODE 3 with-6 hours level not within reactor trip ' limit, breakers open. 880 A.2 Be in MODE 4. [12 hours] 1 B. One required group of B.1 Restore-required-72 hours pressurizer heaters group of pressurizer inoperable. heaters to OPERABLE. status. C. Required Action and C.1 Be in MODE 3. '6 hours associated Completion Time of Condition B 6HQ not met. C.2 Be'in MODE 4. [12 hours] CE0G STS 3.4-20 06/18/90 m .m. -- & a g ,....m- -l,. ,, g ,p

Pressurizer 3.4.9-SURVEILLANCE REQUIREMENTS i SURVEILLANCE FREQUENCY 'SR 3.4.9.1 Verify pressurizer water level 1 (35]%. 12 hours l SR 3.4.9.2 Verify capacity of each required group of 92 days heaters 2-(150] kW. [SR 3.4.9.3 Demonstrate emergency power supply for (18 months] ] pressurizer heaters is OPERABLE. i -CROSS-REFERENCES - None. l l ) l CE0G STS 3.4-21 06/18/90

i Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift .l settings 2 (2475] psia and 1 (2525] psia. 1 .......................---N0TE----------------------------- LCO 3.0.4 and SR 3.0.4 are not applicable for entry into MODES 3 and 4 for the purpose of setting.the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for [36] hours following entry into MODE 3, provided a preliminary cold setting was made prior to heatup. APPLICABILITY: MODES 1, 2, and 3, MODE 4 with any RCS cold leg temperature > (285] F. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer code-A.1 Restore valve to 115 minutes safety valve OPERABLE-status, inoperable. B. Required Action and B.1 Be in MODE 3. 6 hours i associated Completion Time not met. ANQ B.2 Be in MODE 4 with [12 hours] all. RCS cold leg L temperatures s (285]F. p l ~ 1 l CE0G STS 3.4-22 06/18/90 l 1

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS-4 4 SURVEILLANCE FREQUENCY SR 3.4.10.1 Demonstrate each pressurizer safety valve In accordance OPERABLE in accordance with the Inservice with the 4 Testing Program. Inservice Testing Program. i - CROSS-REFERENCES - None. I i i i ( CE0G STS 3.4-23 06/18/90 4

i Pressurizer PORVs 3.4.11-l 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Ooerated Relief Valat (PORVs) LC0 3.4.11 (Two) PORVs and associated block valves shall be OPERABLE. l j APPLICABILITY: MODES 1, 2, and 3. ........................--N0TE----------------------------- LCO 3.0.4 is not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Restore PORV(s) to-1 hour inoperable. OPERABLE status. E A.2 Close the associated I hour block valve (s). B. One or more block B.1 Restore. the block I hour valves inoperable. valve (s) to OPERABLE status. E B.2.1 Close the block I hour valve (s). MD B.2.2 Remove power from I hour-the block valves (s). E (continued) CE0G STS 3.4-24 06/18/90

l Pressurizer PORVs 4 3.4.11 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)l B.3.1 Close PORV.- I hour AliQ B.3.2 . Remove power from. I hour PORV solenoid valve. C. Required Action and C.1 Be 3;. MODE 3. 6 hours associated Completion Time not met. MQ - C.1 Be in MODE 4. [12 hours] SURVEILLANCE REQUIREMENTS SURVEILLANCE' FREQUENCY SR 3.4.11.1

NOTE--------------------

Surveillance not required with block valve closed in accordance with the Required l-Actions of this LCO. Perform one complete cycle of each block 92 days valve. 1 SR 3.4.11.2 Perform a CHANNEL CALIBRATION for each PORV. [18 months] 'SR 3.4.11.3 Perform one complete cycle of each PORV. [18 months]' (continued) 1 CE0G STS 3.4-25 06/18/90

4 Pressurizer PORVs-3.4.11 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY 1 [SR3.4.11;4 Demonstrate emergency power supply for. PORVs (18 months) ]- and block valves is OPERABLE. l CROSS-REFERENCES TITLE NUMBER Low Temperature Overpressure Protection System. 3.4.12 4 i CE0G STS-3.4-26 06/18/90

i LTOP 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temoerature Overoressure Profection (LTOP) System LCO 3.4.12 A LTOP System shall be OPERABLE with a maximum of (one] High Pressure Safety Injection (HPSI) pump OPERABLE, and: a. Two Power Operated Relief Valves (PORVs) with lift 3 seetings s (450] psig, or i 1 b. The RCS de)ressurized with an open RCS vent of 2 (1.3] l square incies. APPLICABILITY: MODE 4 with any RCS cold leg temperature s (285]'F, MODE 5, MODE 6 with the reactor vessel head on ..........................-N0TE----------------------------- LC0 3.0.4 is not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i A. More than (one] HPSI A.1 Initiate action to Immediately pump OPERABLE. ensure a maximum of [one] HPSI pump i OPERABLE. 1 B. One PORV inoperable. B.1 Restore PORV to 7 days OPERABLE status. 1 I C. Required Action and C.1 Depressurize RCS and 8 hours I associated Completion establish RCS vent Time not met, of 2 (1.3] square inches. DB Both PORVs inoperable. 1 CE0G STS 3.4-27 06/18/90

l LTOP' 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of (one) HPSI pump-Within 15 OPERABLE.- minutes prior to decreasing temperature to s (285)*F atiQ 12 hours I i SR.3.4.12.2 Verify required RCS vent open: a. For unlocked-open vent valves, and 12 hours b. For locked-open vent valves. 31 days SR 3.4.12.3 Verify-the block valve open for each-72 hours required PORV. SR 3.4.12.4

NOTE---------------------

31 days-SR 3.0.4 is not applicable. Perform a CHANNEL FUNCTIONAL TEST on each required PORV (excluding PORV actuation). SR 3.4.12.5 Perform a CHANNEL CALIBRATION for each [is months)- required PORV actuation channel. 4 CE0G STS 3.4-28 06/18/90

LTOP 3.4.12 CROSS-REFERENCES TITLE- -NUMBER RCS Pressure and' Temperature Limits 3,4.3 Pressurizer Power Operated Relief Valves 3.4.11 l l 1 CE0G STS 3.4-29 06/18/90 w ,w-,e,. y e

RCS Operational Leakage A 3.A.13' 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational-LEAKAGE shall be limited to the following: a. No Pressure Boundary LEAKAGE b. 1 gpm Unidentified LEAKAGE c. 10 gpm Identified LEAKAGE d. I gpm total primary-to-secondary LEAKAGE through all steam generators and e. (720] gallons per day primary-to-secondary LEAKAGE through any one steam _ generator. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS LEAKAGE not A.1 Reduce LEAKAGE to 4 hours within limits for within limit, reasons other than Pressure Boundary LEAKAGE. B. Required Action and B.1 Be in MODE 3, 6 hours associated Completion Time of Condition A AHQ not met. B.1 Be in MODE 5. 36 hours QR Pressure Boundary LEAKAGE exists. CE0G STS 3.4-30 06/18/90

\\ L RCS Operational Leakage. 3.4.13-g SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY l- ........'..........N0TE-------------------

NOTE-----

SR 3.0.4 is not applicable for entry into Only required l MODES 3 and 4. during_ steady -state opera-tion. L SR 3.4.13.1 Perform a RCS water inventory balance. 72 hours = CROSS-REFERENCES i TITLE NUMBER i RCS Pressure Isolation Valve Leakage. 3.4.14 - 4 RCS Leakage Detection Instrumentation. 3.4.15 Secondary Specific Activity. 3.7.5 4 4 I ( i CE0G STS 3.4-31 06/18/90-i ,,-----,....._~...m--..

(- RCS PIV Leakage 1.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14' RCS Pressure Isolation Valve (PIV) Leakaae l ~LC0 3.4.14 Leakage from each RCS PIV shall be limited to 0.5 gpm per nominal inch of. valve size up to a maximum of 5 gpm at an RCS pressure 2 [2230]_and s (2270] psia. t. i APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS l CONDITION REQUIRED ~ ACTION COMPLETION TIME r A. Leakage from.one or A.1 Restore RCS PIV 4 hours more RCS'PIVs'not -leakage to within within limit. limit. QB - (continued) i CE0G STS 3.4-32 06/18/90.. E -.y 3 e -. -

e RCS PIV Leakage t 3.4.14 l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME' i A.: (continued)

NOTE--------

Each valve used to ~ satisfy Required Action A.2.1 or A.2.2 must have been demonstrated to meet-1 SR 3.4.14.1 and be in the reactor coolant pressure boundary. 4 hours 1 A.2.1 Isolate the high- ~~ pressure portion ~of ~~ the.affected system from tha low pressure portion by use of one closed manual, deactivated automatic or check l valve. i A.N_Q A.2.2 Isolate the high 72 hours pressure portion of the affected system from the low-pressure portion by use of a second closed manual, deactivated' automatic or check valve. B. Required Action and B.1 Be in MODE 3.- 6 hours associated Completion Time not met. AND B.2 Be in MODE 5.- 36 hours CEOG STS 3.4-33 06/18/90 l m. w e -w e

RCS PlV Leakage 3.4.14 j. SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY 1 SR 3.4.14.1

NOTE---

SR 3.0.4 is not applicable for entry into MODES 3 and 4 for the purpose of testing the i isolation valves. i Verify leakage from each RCS PIV limited to (18' months) 0.5 gpm per nominal inch of valve size up to 1 a maximum of 5 gpm, at a RCS pressure 1 687 (2230] and 1 (2270] psia. Prior to entering MODE 2 whenever the plant has been in MODE-5'for 7 days j or more, if leakage i testing has not been performed in 'the previous-9 months Alf i Within 24 hours following valve-actuation due to' automatic or manual i action'or flow through the valves .i (continued)' CE0G STS 3.4-34 06/18/90

RCS PIV Leakage' 3.4.14' SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY [SR 3.4.14.2 Verify Shutdown Cooling (SDC) System auto- [18 months) ] closure interlock prevents the valves from being opened with a simulated or actual RCS pressure signal 2 [' ] psig. (SR 3.4.14.3 Verify SDC. System autoclosure interlock-(18 months] ] caused the valves to close automatically with a simulated or actual RCS pressure 1 signal 2 ( ) psig. CROSS-REFERENCES TITLE NUMBER RCS Operational Leakage 3.4.13 RCS Loops - MODE 4 3.4.6 Safety Injection Tanks 3.5.1 ECCS Trains - Operating - 3.5.2 Containment Isolation Valves 3.6.3 I 4 CEOG STS 3.4-35 06/18/90 a ,-.c.

p RCS Leakage Detection Instrumentation s 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS leakaae Detection Instrumentation ] LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE: a. One' containment sump monitor, and b. One containment atmosphere radioactivity monitor (gaseous or particulate),.[and c. One containment air cooler condensate flow rate-monitor.) i APPLICABILITY: MODES 1, 2,_3 and 4. -ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i A. Required containment A.1 Perform SR 3.4.13.1. Once per 24; i sump monitor inoper-hours able. 6HQ i A.2 Restore containment 30 days sump monitor to OPERABLE status.- (continued): i CEOG STS 3.4-36 06/18/90~ w

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1.1 Take andianalyze Once per 24 atmosphere radio-grab samples of the hours 1 activity monitor containment inoperable, atmosphere. QB B.l.2 . Perform SR 3.4.13.1. Once per 24 hours 4 (MQ B.2 ' Restore containment-30 days) atmosphere radioactivity monitor to OPERABLE status., j i 1 1 (C.Requiredcontainment. C.1 Take and analyze-Once per 24 ] 3 air cooler condensate grab samples of the hours flow rate monitor containment-inoperable. atmosphere. 1 QB C.2 Perform SR 3.4.13.1 Once per 24 hours [D. Required. containment D1 Restore containment 30 days ) atmosphere atmosphere radioactivity and radioactivity 3 containment air monitor.to OPERABLE cooler condensate

status, s

flow rate monitor inoperable. QB D.2 Restore containment ~ 30 days air cooler con-densate flow rate monitor to OPERABLE status. (continued) CEOG STS 3.4-37 06/18/90-l

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required Actions and-E.1 Be in MODE 3. 6 hours-associated Completion Times not met. AND j E.2 Be in MODE 5.- 36 hours F. All required monitors F.1 Enter LC0 3.0.3 Immediately inoperable. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform a CHANNEL CHECK'of the required (12 hours] containment atmosphere radioactivity-l monitors. SR 3.4.15.2 Perform a CHANNEL FUNCTIONAL TEST lof the 30 days l required containment atmosphere. ( radioactivity monitors. l SR 3.4.15.3 Perform a CHANNEL CALIBRATION of the (18 months) recuired containment atmosphere racioactivity monitors. (continued) 4 l CEOG STS -3.4-38 06/18/90 .-...,,...-,,.....n

3 l'. RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS-(continued) SURVEILLANCE FREQUENCY i SR 3.4.15.4 Perform a CHANNEL CALIBRATION of the (18 months) containment sump monitor. I (SR 3.4.15.5 Perform a CHANNEL CALIBRATION of the (18 monith:] ] 1 required containment air cooler condensate i flow rate monitor. ~ CROSS-REFERENCES TITLE NUMBER RCS Operational Leakage 3.4.13 CEOG STS 3.4-39 06/18/90 ll

RCS Specific Activity 3.4.16 ~ 3.4 ~REACTORCOOLANTSYSTEM-(RCS) 3.4.16 RCS Soecific Activity LCO 3.4.16-The specific activity of the primary coolant shall be limited to-

a. A gross specific activity 5100/E pCi/gm, and

b. A DOSE EQUIVALENT I-131 specific activity 1 1.0 t

yCi/gm. 'i APPLICABILITY: MODES 1 and 2, MODE 3 with T,, 2 (500]'F. ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME i A. Gross specific A.1 Determine DOSE 4 hours activity of the EQUIVALENT I-131. primary coolant not within limit. E A.2 Be in MODE 3 with 6 hours T,, < 500'F. b B. DOSE EQUIVALENT B.1 Demonstrate DOSE 0nce per 4 1 1-131 > 1.0 pCi/gm. EQUIVALENT I-131 hours within the-acceptable region of Figure 3.4.16-1. E B.2 Restore' DOSE 48 hours EQUIVALENT I-131 to within limit'. (continued) l CEOG STS 3.4-40 06/18/90 1 ,c w -,.n. ,n. a e

..I RCS Specific Activity 3.4.16 ACTIONS (continued) CONDITION REQUIRED ACTION ' COMPLETION TIME i C. Required Actions and. C.1 Be in MODE 3 with 6 hours associated Completion T,, < (500)'F. Times of Condition B not met, i QB DOSE EQUIVALENT I-131 in the unacceptable - i region of Figure 3.4.16-1, q -. ~. CE0G STS 3.4-41 06/18/90

i RCS Specific Activity 3.4.16 ~ i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Demonstrate primary coolant gross specific 72 hours activity s 100/E pCi/gm. l i SR 3.4.16.2 Demonstrate primary coolant DOSE EQUIVALENT 14 days 5-131 specific activity 1 1.0 yCi/gm. i AND Between 2 and 6 hours after THERMAL POWER-t change 1 15% of RTP within a 1-hour, period. i SR 3.4.16.3

NOTE-----------------

NOTE-----

1. SR 3.0.4 is not applicable. Only required 'in MODE 1. 2. Sample after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last suberitical for 2 48 hours. Determine L. 184 days l CROSS-REFERENCES - None. CE0G STS 3.4-42 06/18/90 6

q RCS Specific Activity 3.4.16 1 .) h This Figure for Illustration Only Do.Not Use for-Operation', ) 'I l ) i i 1 FIGURE 3.4.16-l_ (Page l' of 1) DOSE EQUIVALENT I-131-Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0yCi/ gram Dose Equivalent.1-131. 9 l L CE0G STS 3.4-43 06/18/90 r y l +

RCS Loops --Test Exceptions D 3.4.17. 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Looos - Test Exception-LCO 3.4.17 The requirements of LC0 3.3.1 (RPS Instrumentation) for the [(Analog) RC Flow-Low, Thermal Margin / Low Pressure, and Asymmetric Steam Generator Transient Protective Trip Functions) [(Digital) High Log Power,. High local Power Density, Low DNBR Protective Trip Functions) may be suspended provided: s. THERMAL POWER does not exceed 5% of RTP, and b. Tho reactor trip setpoints of the OPERABLE power level channels are set s 20% of RTP-. i APPLICABILITY: During startup'and' PHYSICS TESTS. ACTIONS CONDITION REQUIRED ACTION. COMPLETION TIME A.- THERMAL POWER not A.1 Open reactor trip Immediately within limit, breakers. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify THERMAL POWER $ 5% of RTP. I hour SR 3.4.17.2 Perform a CHANNEL FUNCTIONAL TEST on each 12 hours-logarithmic power level and. linear power prior to level neutron flux monitoring channel, initiating startup or PHYSICS TESTS L CE0G STS 3.4-44 06/18/90 -w v - - we= s .-wwwwww v = - - -- =*---w- -, -v<-,'%-+ v

RCS Loops Test Exceptions 3.4.17 CROSS-REFEREPCES TITLE NUMBER s 3.3.1 Reactor Trip System Instrumentation RCS Loops - MODES 1 and 2, 3.'4. 4 - l CE0G STS 3.4-45 06/18/90 N

y+ RCS Pressure, (emperature, and Flow DNB Liaits

3. 4.1 y

3.4 REACTOR COOLANT SYSTEM (RCS) s 3.4.1 RCS Pressure. Temoerature. and Flow DNB Limits ~ LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average. temperature, and RCS total flow rate shall be within the limits provided below: a. Pressurizer pressure 2-(2200] psig, f b. RCS average temperature 5 (581]'F, and c. RCS total flow rate 2 ( ) gpm. i .1 APPLICABILITY: MODE 1. R 'l ...........................N0TE---------------------------- Pressurizer pressure limit does not-apply'during: a. A THERMAL POWER ramp in excess of (5]% of RATED THERMAL POWER (RTP) per minute, or ~ b. A THERMAL POWER step in excess of (10]% of RTP. l ACTIONS i l CONDITION REQUIRED ACTION COMPLETION TIME - t A. One or more RCS'DNB A.1 Restore RCS DNB '2 hours' parameters not within' parameter (s)Lto. limit (s), within limit. l l. I .i B. Required Action and-B.1 Be in MODE 2. 6 hours 4 associated Completion Time not met. L l ) -WOG STS 3.4-1 06/18/90 t g....... ,e,

RCS Pressure, Temperature, and Flow DNB Licits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure 2 (2200) psig. 12 h'urs o SR 3.4.1.2 Verify RCS average temperature s (581)'F. 12 hours l SR 3.4.1.3-Verify RCS total flow rate 1 ( )gpm. 12 hours SR 3.4.1.4 ..-.---...-.-..--N0TE-- SR 3.0.4 is not applicable. This SR shall be performed within 24 hours after reaching 90% of RTP. Demonstrate, by precision heat balance, that (18 months) RCS total flow rate is e [ ] gpm. CROSS REFERENCES TITLE NUMBER Reactor Core Safety Limi'.s 2.2.1 RCS Loups - h0 DES 1 and 2 3.4.4 l WOG STS 3.4-2 06/18/90 , + + - - -, .,-.--,n ,-,,a-,--..e-w

l 3.4 REACTORCOOLANYSYSTEM(RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature shall be 1 (541)'F. APPLICABILITY: MODE 1 lwith one or more RCS loop average temperatures < 1;551)'F), MODE 2 with (one or more RCS loop average temperatures < (551)'F ) ken 2 1.0. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1 A. One or more RCS loop A.1 Restore RCS loop 15 minutes average temperatures average tempera-not within limits. ture(s) to within limit. QB A.2 Be in MODE 3. 30 minutes WOG STS 3.4-3 06/18/90 i O

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS loop average temperature in each Within 15 loop 2 (541]'F. minutes prior to achieving criticality AND ..... NOTE --- Only required 2 deviaI. Ton)ref if(T -T j alarm not - reset 30 minutes i CROSS-REFERENCES TITLE NUMBER 1 MODE 2 Physics Test Exceptions 3.1.12

I t

e % v ) i WOG STS 3.4-4 06/18/90 . mm. ._,___..._,....._.......,_,.......y..._.y. ,m,

RCS P/T Liaits = 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temoerature (P/T) Limits LCO 3.4.3 The combination of RCS pressure, except pressurizer pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within the limits specified in the PRESSURE AND TEMPERATURE LIMITS REPORT. APPLICABILITY: At all times, i i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME ............N0TE--------- All Required Actions must be completed whenever this Condition is entered. A. Requirements of LCO A.1 Restore parameter (s) 30 minutes not met. to within limits. 88Q A.2 Determine RCS is 72 hours acceptable for continued operation. l l B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5 with 36 hours RCS pressure < (500] psig.. WOG STS 3.4-5 06/18/90

RCS P/T Liaits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the combination of RCS pressure and

NOTE----

RCS temperature and the heatup and cooldown Only required rates within limits. during RCS heatup and cooldown operations and in-service leak and hydro-static testing. 30 minutes CROSS-REFERENCES TITLE NUMBER Reactor Core Safety Limits 2.1.1 Reactor Coolant System Pressure Safety Limit 2.1.2 j RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 RCS Minimum Temperature for Criticality 3.4.2 l Low Temperature Overpressure Protection System 3.4.12 l l I WOG STS 3.4-6 06/18/90 .---m---+--,s

v. - - -.

-.w,. --ev$-

l RCS Loops -MODES 1 and 2 l s 3.4.4 i 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loon - MODES 1 and 2 LCO 3.4.4 (Four) RCS loops shall be OPERABLE and in operation. 1 APPLICABILITY: MODES I and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS loops A.1 Be in MODE 3. 6 hours not in operation. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop in operation. 12 hours SR 3.4.4.2 Demonstrate steam generator tube integrity In accordance in accordance with the Steam Generator Tube with the 4 Surveillance Program (Specification Steam 5.8.4.p). Generator Tube Surveil-lance Program (Specifica-tion 1 5.8.4.p). i 9 WOG STS 3.4-7 06/18/90 ,,,-e.-- a-e e - - -.. --,-,w-v -a

RCS Loops MODES 1 and 2 3.4.4 CROSS REFERENCES TITLE NUMBER RCS Loop Isolation Valves 3.4.17 RCS Loops Test Exception 3 3.4.19 e t WOG STS 3.4-8 06/18/90

RCS Loops MODE 3 3.4.5 3.4 . REACTOR COOLANT SYSTEM (RCS) i 3.4.5 RCS Loons - MODE 3 LCO 3.4.5 (Two) RCS loops shall be OPERABLE, and a. (Two) RCS loops shall be in operation when the reactor trip breakers are closed, or b. One RCS loop shall be in operation when'the reactor' trip breakers are open. .........................N0TE------------------------------ All Reactor Coolant Pumps (RCPs) may be de-energized for up to I hour per 8 hour period provided: a. No o)erations are permitted that would cause reduction i of tie RCS boron concentration, and b. Core outlet temperature is maintained at least 10'F below saturation temperature. APPLICABILITY: MODE 3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Restore required RCS 72 hours inoperable. loop to OPERABLE status. B. Required Action and B.1 Be in MODE 4. 12 hours associated Completion Time of Condition A not met. (continued) l WOG STS 3.4-9 06/18/90 e a ,,e w ,--n.

RCS Loops MODE 3 i 3.4.5 i ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Only one RCS loop in C.1 Restore one RCS loop I hour operation and reactor to operation. trip breakers closed. QB C.2 Open reactor trip 1 hour breakers. P D. No RCS loop in D1 Open reactor trip Immediately operation. breakers. MiQ D.2 Suspend all opera-Imediately tions involving a reduction in RCS boron concentration. A!fD D.3 Initiate action to Imediately restore on RCS loop to operation.- l WOG STS 3.4-10 06/18/90 +

RCS Loops. MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY .t SR 3.4.5.1 Verify required number of RCS loops 12 hours operating. SR 3.4.5.2 Verify steam generator secondary-side water 12 hours level ;t (17)% for required OPERABLE RCS loops. .....................N0TE-Only required if reactor trip breakers are open. SR 3.4.5.3 Verify correct breaker available alignment 7 days and indicated power to the required pump that is not in operation. F CROSS REFERENCES - None, 1 i WOG STS 3.4 11 06/18/90 4 ~. g m

RCS Loops MODE 4 3.4.6 4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Looos - @p(_( LCO 3.4.6 Two loops consisting of any combination of RCS loops and Residual Heat Removal (RHR) loops shall be OPERABLE, and at least one loop shall be in operation. ..........................N0TE-------- 1. All RCPs and RHR pumps may be de-energized for up to I hour per 8 hour period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration, and

b. Core outlet temperature is maintained at least 10'F below saturation temperature.

2. No RCP shall be started with one or more RCS cold leg temperatures s (275)*F unless the secondary-side water temperature of each Steam Generator (SG) is < [ ]*F above cach of the RCS cold leg temperatures. i t APPLICABILITY: MODE 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Only one RCS loop A.1 Initiate action to 15 minutes OPERABLE return a second loop to OPERABLE status. A@ No RHR loops OPERABLE. i (continued) WOG STS 3.4-12 06/18/90

RCS Lcops MODE 4 3.4.6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Only one RHR loop B.1 Restore a second I hour OPERABLE loop to OPERABLE status. M QB No RCS loops OPERABLE. B.2 Be in MODE 5. 25 hours C. No loop in operation. C.1 Suspend all opera-Immediately tions involving a reduction in RCS boron concentration. M C.2 initiate action to Immediately restore one loop to operation. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify SG secondary side water levels 1 12 hours (17]% for required OPERABLE RCS loops. SR 3.4.6.2 Verify at least one RHR or RCS loop 12 hours f operating. I i SR 3.4.6.3 Verify correct breaker alignment and 7 days t indicated power available to the required pump that is not in operation. i I WOG STS 3.4-13 06/18/90 l

RCS Loops - MODE 4 3.4.6 CROSS-REFERENCES l TITLE NUMBER l l ECCS Trains - Shutdown 3.5.3 Low Temperature Overpressure Protection System 3.4.12 l WOG STS 3,4-14 06/18/90-l L

RCS Loops - MODE 5 Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Reactor Coolant loops and Circulation. MODE 5. Looos Filled LCO 3.4.7 One RCS loop or one Residual Heat Removal (RHR) loop shall be OPERABLE and in operation, and either: a. One additional RHR loop shall be OPERABLE, or b. The secondary-side water level of at.least (2) Steam Generators (SGs) shall be 2 (17]%. ...........................-N0TES--------------------------- 1. The RCP or RHR pump of the loop in operation may be de-energized for up to I hour per 8-hour period provided-

a. No operations are permitted that would cause reduction of the RCS boron concentration, and

b. Core outlet temperature is maintained at least 10'F below saturation temperature.

2. One RHR loop may be inoperable for u) to 2 hours for surveillance testing provided that tie other RHR loop is OPERABLF. and in operation. 3. No reactor coolant pump shall be started with one or more RCS cold leg temperatures s (275]*F unless the I secondary side water temperature of each SG is 1 ( ]'F above each of the RCS cold leg temperatures. APPLICABILITY: MODE 5 with RCS loops filled. WOG STS 3.4-15 06/18/90 l

RCS Loops - MODE 5, Loops Filled ?.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Only one loop A.1 Initiate action to 15 minutes OPERABLE. restore a second-loop to OPERABLE ANQ status. Less than (2) SGs QB with secondary side water levels within A.2 Initiate action to 15 minutes limit. restore required SG secondary side water levels to within limits. B. No RHR loop OPERABLE. B.1 Suspend all Innediately operations involving QB a reduction in RCS boron concentration. No RHR or RCS loop.in operation. aHQ B.2 Initiate action to Immediately restore one RHR or RCS loop to OPERABLE status and operation. WOG STS 3.4-16 06/18/90 I

RCS Loops o MODE 5, Loops Filled i 3.4.7 I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1. ..... NOTE----- Only required j if only one ] RHR loop is OPERABLE. SR 3.4.7.1 Verify SG secondary-side water levels 2 12 hours (17)% in at least (2) steam generators. l 1 SR 3.4.7.2 Verify at least one RHR or RCS loop 12 hours ) operating. ~ I .....N0TE----- Only required if secondary-side water level is s (17]% in more than (2) SGs. SR 3.4.7.3 Verify correct breaker alignment and 7 days indicated power available the required RHR loop that is not in operation. ~ ~ ~ CROSS-REFERENCES l TITLE NUMBER l RCS Loops. Mode 5, Loops Not Filled 3.4.8 ) l L Low Temperature Overpressure Protection System 3.4.12 WOG STS. 3.4-17 06/18/90 l l

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Looos - MODE 5. Looos Not Filled LCO 3.4.8 Two Residual Heat Removal (RdR) loops shall be OPERABLE and at least one RHR loop shall be in operation. ..........................N0TES-One RHR loop may be inoperable for up to 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation. APPLICABILITY: MODE 5 with RCS loops not filled. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to 15 minutes inoperable, restore RHR loop to OPERABLE status. (continued) WOG STS 3.4 18 06/18/90 4

\\ l RCS Loops o MODE 5, Loops Not Filled j 3.4.8 l j i ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME I B. No RHR loop B.1 Suspend all Immediately OPERABLE. operations involving reduction in RCS QB boron concentration, j No RHR loop in AND operation. B.2 Initiate action to Immediately restore one RHR loop J to OPERABLE status and operation. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-SR 3.4.8.1 Verify at least one RHR loop operating.- 12 hours t SR 3.4.8.2 Verify correct breaker alignment and 7 days indicated )ower availabile to the required RHR loop t1at is not in operation. CROSS-REFERENCES TITLE NUMBER-RCS Loops MODE 5, 8 oops Filled 3.4.7 ) Low Temperature Overpressure Protection System 3.4.12 'l WOG STS 3.4-19 06/18/90

Pressurizer 3.4.9 i 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with. j a. Pressurizer water level s [ ]% of span, equivalent f to5(1656)cubicfeet,and b. At least two groups of pressurizer heaters OPERABLE with the capacity of each group 1 [150) kW and capable of being powered from an emergency power source. APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONN 1 TION REQUIRED ACTION COMPLETION TIME ~ A. Preu ster water A.1 Be in MODE 3 with 6 hours level not within reactor trip

limit, breakers open.

AND A.2 Be in MODE 4. 12 hours B. One required group of B.1 Restore required 72 hours pressurizer heaters group of pressurizer inoperable. heaters to OPERABLE i status. I C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition 8 ANQ not met. C.2 Be in MODE 4. '12 hours i WOG STS 3.4-20 06/18/90 j e n .-.v.,

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level s [ ]% of 12 hours span. SR 3.4.9.2 Verify capacity of each required group of 92 days pressurizer heaters 2 (150) kW. (SR 3.4.9.3 Demonstrate emergency power supply for (18 months) ) pressurizer heaters is OPERABLE. CROSS REFERENCES TITLE NUMBER Reactor Trip System Instrumentation Function 10 3.3.1 l t { WOG STS 3.4-21 06/18/90 u v 9

\\ Pressurizer Safety Valves 3.4.10 1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves I LCO 3.4.10

Three) pressurizer safety valves shall be OPERABLE with

.ift settings 2 (2460) and $ (2510) psig. ..........................N0TE LC0 3.0.4 and SR 3.0.4 are not applicable for entry into MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for (54) hours, provided a preliminary cold setting was made prior to heatup. i APPLICABILITY: MODES 1, 2, and 3, MODE 4 with one or more RCS cold leg temperatures > [275)*F. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME-A. One pressurizer A.1 Restore valve to 15 minutes safety valve OPERABLE status. inoperable. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. 6hD 8.2 Be in MODE 4 with 12 hours all RCS cold leg temperatures s (275)'F. WOG STS 3.4-22 06/18/90 e e .---,e .Q.. ,e

\\ ~ Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4,10.1 Demonttrate each pressurizer safety valve In accordance OPERABLE in accordance with the Inservice with the Testing Program. Inservice Testing Program. CROSS REFERENCES - None. l l O i WOG STS 3.4-23 06/18/90 9 e .n,- ,r-e n e w--

,-4

i Pressurizer PORVs 3.4.11 t 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Ooerated Relief Valves (PORVs) LCO 3.4.11 Each PORY and associated block valve shall be OPERABLE.. APPLICABILITY: MODES 1, 2, and 3. ..........................N0TE -- -------- --~~- ----- - -- LCO 3.0.4 is not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore PORV(s) to I hour PORVs inoperable OPERABLE status, and capable of being manually 28 cycled. A.2 Close associated I hour block valve (s). (continued) 1 WOG STS 3.4-24 06/18/90

Pressurizer PORVs 3.4.11 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. One PORV B.1 Restore PORV to I hour inoperable and OPERABLE status, not capable or being manually 03 B.2.1 Close associated I hour block valve. M B.2.2 Remove power from I hour associated block valve. l l B.2.3 Restore PORV to 73 hours OPERABLE status. 1 M B.2.4 Restore power to 73 hours associated block valve. B.2.5 Open associated 73 hours block valve. (continued) b WOG STS 3.4 25 06/18/90- , -. ~, ..\\.,

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Restore block valve I hour inoperable. to OPERABLE status. E C.2.1 Close block valve. I hour E C.2.2 Remove power from I hour block valve. M C.2.3 Restore block valve 73 hours to OPERABLE status. M C.3.1 Deactivate I hour associated PORY by removing power from its solenoid valve. M C.3.2 Restore block valve 73 hours and PORV to OPERABLE status. D. Required Actions and D.1 Be in MODE 3. 6 hours associated Completion Times of Conditions M A, B, or C not met. D.2 Be in MODE 4. 12 hours m (continued) l WOG STS 3.4-26 06/18/90 k

Pressurizer PORVs 3.4.11 ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME E. More than one PORV E.1 Restore PORVs to I hour inoperable and not OPERABLE status, capable of being manually cycled. QB-E.2.1 Close associated I hour block valves. AMQ E.2.2 Remove power from I hour associated block valves. 680 ) E.2.3 Be in MODE 3. 7 hours aND E.2.4 Be in MODE 4. 13 hours (continued) i i i WOG STS 3.4-27 06/18/90 l l t o

Pressurizer PORVs l 3.4.11 ACTIONS (continued) CONDITION REQVIRED ACTION COMPLETION TIME F. More than one block F.1 Restore block I hour valve inoperable, valves to OPERABLE status. ] QB F.2.1.1.1 Close I hour inoperable block valves. ED F.2.1.1.2 Remove power 1 hour i from inoperable block valves. QB F.2.1.2 Deactivate I hour associated PORVs by removing power from their solenoid valves. J MD F.2.2 Be in MODE 3. 7 hours I l F.2.3 Be in MODE 4. 13 hours j s WOG STS 3.4-28 06/18/90 l l [ t

i e Pressurizer PORVs 3.4.11 I SURVEILLANCE REQUIREMENTS I SVRVEILLANCE FREQUENCY ..................-N0TE------------------- Surveillance not required with block valve closed in accordance with the Required Actions of this LCO. i SR 3.4.11.1 Perform one complete cycle of each bicek 92 days valve. SR 3.4.11.2 Perform a CHANNEL CALIBRATION for each PORV. (18 months) SR 3.4.11.3 Perform one complete cycle of each PORV. (18 months) (SR3.4.11.4 Demonstrate emergency power supply for PORVs (18 months) ] and block valves is OPERABLE, CROSS REFERENCES - None. l f r> WOG STS 3.4-29 06/18/90 m m 9

t LTOP 3.4.12 3;4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temoerature Overoressure Protection System LCO 3.4.12 A Low Temperature Overpressure Protection System shall be OPERABLE with a maximum of (one) (high pressure injection] pump OPERABLE, and a.. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PRESSURE AND-TEMPERATURE LIMITS REPORT (PTLR), or (b. Two Residual Heat Removal-(RHR), suction relief valves with setpoints 2 [ ] and 5 [ ] psig, or) (c.- One PORV with nominal' lift settings within the limits specified in the PTLR and one RHR suction relief valve with a setpoint 2 ( ) and 5 [. ] psig, or) d. The RCS depressurized with an open RCS vent of 2 [' ] square inches. j APPLICABILITY: MODE 4 with any RCS cold leg temperature s (275]'F, MODE 5, MODE 6 with the reactor vessel head on. ........................--N0TE---------..--.---...--..-.... LC0 3.0.4 are not applicable. I I L l 0 WOG STS 3.4-30 06/18/90 y +-

LTOP i 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. More than (one) (high A.1 Initiate action to -Immediately pressureinjection) ensure a maximum of pump OPERABLE. (one] [high pressure injection) pump OPERABLE. l B. One required PORV B.1-Restore required 7 days (and two RHR suction PORV [or one RHR relief valves] suction relief i inoperable, valve) to OPERABLE status. C Two required. C.1 Restore the-RHR 7 days PORVs and one suction relief valve i RHR suction or one required PORV relief valve to OPERABLE status. inoperable. D. i do require / 30RVs D.1-Depressurize RCS and 8 hours 4 'v:d two > s -tion establish RCS vent Jf' Jvns) of 2 [ ] square r' + ' vu Le inches. Required Actions and associated Completion Times of Conditions A, B [or C) not met. I WOG STS 3.4-31 06/18/90 A

LTOP' 3.4.12 SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximut of [one] [high pressure Within 15 injection) pump OPERABLE. minutes prior to decreasing temperature to 5 [ ]F MlQ 12 hours SR 3.4.12.2 ------------------NOTE SR 2.0.4 is not applicable. Verify the RHR suction valves are open for 12 hours each required RHR suction relief valve. l SR 3.4.12.3 Verify required RCS vonts open. a. For unlocked-open vent valves, and 12 hours i b. For locked-open vent valves. 31 days SR 3.4.12.4 Verify the block valve open for each 72 hours required PORV. SR 3.4.12-5 Verify required RHR suction isolation valves 31 days are open with power to the valve operator removed. (continued) l 4 WOG STS 3.4-32 06/18/90-m

LTOP L 3.4.12-l L SURVEILLANCE REQUIREMENTS (continued) L SURVEILLANCE FREQUENCY ..................N0TE----------------- .................'is not applicable. SR 3.0.4 SR 3.4.12.6 Perform ANALOG CHANNEL.0PERATIONAL TEST, 31 days excluding valve operation, for each required PORV. SR 3.4.12.7 Perform CHANNEL CALIBRATION for each {18 months]- required PORV. l CROSS-REFERENCES TITLE NUMBER RCS Pressure and Temperature Limits '3.4.3 RCS-Loops - MODE 5, Loops Filled 3.4.7 i RCS Loops - MODE 5, Loops Not Filled 3.4.8 Pressurizer Power Operated Relief Valves 3.4.11 ECCS Trains - Shutdown 3.5.3 Special Report (Reporting Requirement) 1 I WOG STS 3.4-33 06/18/90 ,. ~ _ _...m, s -.+. # ,m. y

RCS Operational LEAKAGE 3.4.13 a .3.4 REACTOR COOLANT SYSTEM (RCS)' 3.4.13 RCS Ooerational LEAKAGE 3 LC0 3.4.13 RCS operational leakage shall be limited to: a. No Pressure Boundary LEAKAGE, b. I gpm Unidentified LEAKAGE, c.- 10 gpm Identified LEAKAGE from-the'RCS, d. 1 gpm total primary-to-secondary LEAKAGE through all steam generators, and e. [500] gallons per day primary-to-secondary LEAKAGE through any one-steam generator. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS LEAKAGE not A.1 - Reduce LEAKAGE to 4 hours within limits for within limit.. reasons other'than Pressure Boundary LEAKAGE. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A ANQ not met. B.2 Be-in MODE 5. 36 hours QB t Pressure. Boundary-LEAKAGE exists. i WOG.STS 3.4-34 06/18/90 r 1

RCS Operational LEAKAGE ~ 3.4.13 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1

NOTE------------------

NOTE-----

SR 3.0.4 is not applicable for entry into Only required MODES 3 and 4. during steady state opera-tion Perform a RCS water inventory balance. 72 hours. CROSS-REFERENCES TITLE NUMBER l RCS Pressure Isolation Valve Leakage. 3.4.14 RCS Leakage Detection-Instrumentation. 3.4.15 l l I I WOG STS 3.4-35 06/18/90 1

o RCS'PIV Leakage s - 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakaae LC0 3.4.14 Leakage from each.RCS PIV shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2 (2215] and s (2255) psia. APPLICABILITY: MODES 1, 2, 3, and 4. i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage from one or-A.1 Restore RCS PIV 4 hours more RCS PIVs not leakage to within within limit. limit. 93 (continued) l i I 1 WOG STS 3,4-36 06/18/9' A/

RCS PIV' Leakage 3.4.14 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

NOTE--------

Each valve used to satisfy Required Action A.2.1 or A.2.2 must-have been demonstrated to meet i SR 3.4.14.1 and be in the reactor coolant pressure boundary. A.2.1 Isolate the high 4 hours pressure portion of the affected system from the low. -pressure portion by I use of one closed manual, deactivated automatic or check

valve, aHD A.2.2 Isolate the high 72 hours pressure portion of the affected system from the low L

pressure portion by l use-of a second . closed manual, deactivated automaticaor check valve. i B. Required Action and, 8.1 Be in MODE 3. 6 hours 1 associated Completion q Time not met. AND B.2 Be in MODE 5. 36 hours \\ WOG STS 3.4-37 06/18/90 9 m

t <9 RCS PIV Leakage. a 3.4.14 SURVEILLANCE REQUIREMENTS i SURVEILLANCE. FREQUENCY u .SR. 3.4.14.1

NOTE-------- '------_------

SR 3.0.4 is not applicable for entry into l MODES 3 and 4 for the purpose of testing,the isolation valves. b Verify leakage from each RCS PIV limited to. (18 months] 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure 1 E (2215] and 1-(2255] psia. Prior to entering MODE 2 whenever the. plant has been in MODE' 5 for 7 days or more, if leakage testing has not been performed in-the previous 9 months M Within 24 hours s following valve actuation due-to automatic or manual action or flow through the valves (continued)- l l-WOG STS 3.4-38 06/18/90; c l it- -w

. g1 RCS PIV Leakage l 3.4.14 l SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY i SR 3.4'.14.2 Demonstrate Residual Heat Removal (RHR) [18 months] System auto-closure. interlock prevents the valves.from being opened with a simulated or actual RCS pressure signal 2 [' ] psig. i SR 3.4.14.3 Demonstrate RHR System auto-clos'ure (18 months) interlock causes the valves to close automatically with a simulated or actual RCS pressure signal'l [ ],psig. 5 CROSS-REFERENCES TITLE NUMBER RCS Loops - MODE 4 3.4.6 RCS Operational Leakage 3.4.13 Accumulators 3.5.1 ECCS Trains - Operating 3.5.2 Containment Isolation Valves -3.6.3 4 WOG STS 3.4-39 06/18/90 e

l-, .I RCS PIV Leakage 3.4.14 l 3.4 REACTOR COOLANT SYSTEM (RCS) 4 3.4.14 RCS Pressure Isolation Valve (PlV) leakaae LC0 3.4.14 Leakage from each RCS PIV shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure ;t [2215) and 5 [2255) psia. l 1 APPLICABILITY: MODES-1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLET!0N TIME A. Leakage from one or A.1 Restore RCS PIV 4 hours-more RCS PIVs not leakage to within within limit. limit. N (continued) i i 9 WOG STS 3.4-36 06/18/90

k. RCS PIV Leakage 3.4.14 b" ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME. A. (continued)

NOTE--------

l Each valve used to l satisfy Required Action A.2.1 or A.2.2 must have been demonstrated to meet SR 3.4.14.1 and be in.the reactor coolant pressure boundary. A.2.1 Isolate the high -4 hours -l pressure portion of-the affected system from the low. pressure portion by-use of one closed a manual,-deactivated-automatic or check valve. aHD A.2.2 ' Isolate the high 72 hours pressure portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic or check-valve. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion-Time.not met. ANQ i B.2 Be in MODE'5. 36 hours-t WOG STS '3.4-37 06/18/90 l ^ m - ~ =

.RCS PIV Leakage- .c 3.4.14 i SVRVEILLANCE REQUIREMENTS SURVEILLANCE ' FREQUENCY l SR 3.4.14.1

NOTE----------------------

SR 3.0.4 is not applicable for entry into MODES 3 and 4 for the purpose of testing the isolation valves, i Verify leakage from each RCS PIV limited to (18 months] 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure 1 AMQ' (2215] and s (2255] psia. Prior to entering MODE 2 whenever 4 the plant has been in MODE 5 for 7 days or more, if' leakage testing'has .not been performed in the previous 9 months AMQ Within 24 i hours-i following: valve actuation due-to automatic or manual action or-flow through the valves-(continued) 9 WOG STS 3.4-38 06/18/90 l

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS (continued) SVRVEILLANCE FREQUENCY 4 SR 3.4.14.2 Demonstrate Residual Heat Removal (RHR) (18 months) System auto-closure interlock prevents 'the valves from being opened with a simulated or actual RCS pressure signal 2 ( ) psig.: SR 3.4.14.3 Demonstrate RHR System auto-closure (18 months) interlock causes.the valves to close automatically with a simulated or actual RCS pressure signal 1 [ -] psig, CROSS REFERENCES TITLE NUMBER RCS Loops - MODE 4 3.4.6 RCS Operational Leakage 3.4.13 Accumulators 3.5.1 ECCS Trains - Operating 3.5.2 Containment Isolation Valves 3.6.3 WOG STS 3.4-39 06/18/90'

RCS Leakage Detection Instrumentation 3.4.15 ~ 3.4 REACTOR COOLANT SYSTEM (RCS) 13.4.15 RCS Leakaae Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE: a. One containment sump (level or discharge flow) monitor, and-b. One containment atmosphere radioactivity monitor (gaseous or particulate),. [and c. One containment air cooler condensate flow rate monitor.) APPLICABILITY: MODES 1, 2, 3 and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 Perform SR 3.4.13.1. Once per 24 sump monitor inoper-hours able. AND A.2 Restore containment 30 days sump monitor to OPERABLE status. (continued) 9 ~WOG STS 3.4-40 06/18/90

RCS Leakage Detection Instrumentation 3.4.15-ACTIONS (continued) CONDITION REQUIRED' ACTION COMPLETION TIME B. Required containment B.1.1 Take and analyze Once per 24 atmosphere radio-grab samples of the hours activity monitor. containment inoperable. atmosphere. .QB B.I.2-Perform SR 3.4.13.1. Once per 24 hours 1 [At(D 8.2 Restore containment 30 days) atmosphere radioactivity monitor to OPERABLE e status. [C. Required containment C.1 Take and analyze Once per 24') air cooler condensate grab samples of the hours [ flow rate monitor containment ( inoperable, atmosphere. QB C.2 Derform SR 3.4.13.1 Once per 24 hours (D. Required containment D.1 Restore'. containment 30 days ] atmosphere atnosphere i radioactivity and racioactivity containment air monitor to OPERABLE cooler condensate

status, flow rate monitor inoperable.

QB D.2 Restore containment 30 days air cooler con-densate flow rate j monitor to OPERABLE status. I (continued) WOG STS 3.4 41 06/18/90 g

RCS Leakage Detection Instrumentation "E 3.4.15 ACTIONS'(continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required Actions and E.1 Be in MODE 3. 6 hours-associated Completion Times not met. ANQ E.2 Be in MODE 5. 36 hours F. All required monitors F.1 Enter LC0 3.0.3 Immediately inoperable. t. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform a CHANNEL CHECK of required [12 hours] containment atmosphere radioactivity monitor. SR 3.4.15.2 Perform a ANALOG CHANNEL OPERATIONAL TEST of 30 days required containment atmosphere radioactivity monitor.- SR 3.4.15.3 ' Perform CHANNEL CALIBRATION of required (18 months) containment atmosphere radioactivity monitors. (continued) WOG STS 3.4 42 06/18/90

+ RCS' Leakage Detection Instrumentation 3.4.15 ~ SURVEILLANCE REQUIREMENTS (continued) a . SURVEILLANCE FREQUENCY-o i SR 3.4.15.4 Perform CHANNEL CALIBRATION of containment (18 months) sump monitor. (SR 3.4.15.5 Perform CHANNEL CALIBRATION of required (18' months) ) 4 containment air cooler condensate flow rate monitor. -t t 7 1 CROSS-REFERENCES TITLE NUMBER RCS Operational LEAKAGE 3.4.13 i I. l-i l l l WOG STS 3.4-43 06/18/90 4

RCS Specific Activity' 3.4.16 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.16 RCS Soecific Activity 4 LCO 3.4.16 The specific activity of the primary coolant shall be limited to: a. A gross specific activity 5100/t pCi/g, and b. A DOSE EQUIVALENT I-131 specific activity 1-1.0 yCi/g. APPLICABILITY: MODES I and 2, ) MODE 3 with RCS average temperature 1500'F. ACTIONS CONDITION ~ REQUIRED ACTION COMPLETION. TIME A. Gross specific A.1 Determine DOSE 4 hours activity of the EQUIVALENT I-131, primary coolant not within limit. E A.2-Be in MODE 3 with 6 hours .RCS.averag'e tempera-ture < 500 F. B. DOSE EQUIVALENT I-131 B.1 Determine DOSE Once per 4 > 1.0 #Ci/g. EQUIVALENT I-131. hours .E B.2 Restore specific 48 hours activity to within limit. -(continued) WOG STS 3.4-44 06/18/90 I L .l

RCS Specific Activity ) 3.4.16 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Actions and C.1 Be in MODE 3 with 6 hours associated Completion 'RCS average Times of Condition B temperature < 500'F. not met. 9.B DOSE EQUIVALENT I-131 in the unacceptable region of Figure-3.4.16-1. } u ( l l WOG STS 3.4-45 06/18/90 ,.S

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Demonstrate primary coolant gross specific 72 hours activity s 100/E pCi/g. SR 3.4.16.2 Demonstrate primary coolant-DOSE EQUIVALENT 14 days I-131 specific activity 5 1.0 pCi/g. AMl Between 2 and 6 hours after a THERMAL POWER change of 215% of RATED THERMAL POWER within a 1-hour period.- SR 3.4.16.3

NOTES-------------------

NOTE-----

1. SR 3.0.4 is not applicable. Only required in MODE 1 2. Sample after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed -since the reactor was last suberitical for 2 48 hours. Determine E. 184 days l-l l l CROSS REFERENCES - None, i I 1 L WOG STS 3.4-46 06/18/90 l

RCS Specific Activity I -3.4.16 i .1 1!:; r l i$ Figure 3.4.16-1 (Page 1 of 1) i Reactor Coolant DOSE EQUIVALENT I-131 Specific Activity Limit l. Versus Percent of RATED THERMAL POWER 3 i l l l WOG STS 3.4-47 06/18/90 l 1 l~

RCS Loop-Isolation Valves 3.4.17 l l L 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS LooD Isolation Valves LC0 3.4.17 Each RCS hot and cold leg loop isolation valve shall be open with power removed from each isolation valve operator. l APPLICABILITY: MODES 1, 2, 3, and 4 l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Power available to A.1 Remove power from 30 minutes one or more loop' loop isolation valve isolation valve operators. operators. B.

NOTE--------

B.1 Maintain valve (s) Immediately All Required Actions closed. must be completed whenever this MQ Condition is entered. B.2 Be in MODE 4. 6 hours One or more RCS loop MD isolation valves closed. B.3 Be in MODE 5. .36 hours l l WOG STS 3.4-48 06/18/90 l I

RCS Loop Isolation Valves. 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1, Verify each RCS loop isolation valve open 31 days and power removed from each loop isolation valve operator. CROSS REFERENCES TITLE NUMBER RCS Isolated loop Startup 3.4.18 } i WOG STS 3.4-49' 06/18/90 6 . ~ -

a b# RCS Isolated Loop Startup-3.4.18 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.18 RCS Isolated loop Startuo' j LCO 3.4.le Each RCS isolated loop ~ shall remain isolated with: a. The' hot and cold leg isolation valves closed if boron concentration of the isolated loop is < boron concentration of the operating-loops, and b. The cold leg isolation valve closed if the cold leg i temperature of'the isolated loop is > [ ]'F below the highest cold leg temperature of the operating loops.. ? APPLICABILITY: MODES S and 6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l A. Isolated loop hot or A.1

NOTE-------

cold leg isolation Only_ required if i valve open prior to boron concentration meeting LCO requirement not met, requirements. Close hot and cold Immediately leg isolation valves. QE A.2

NOTE-------

Only required if temperature require-ment not met. \\ Close cold leg Immediately isolation valve. WOG STS 3.4-50 06/18/90

RCS-Isolated Loop Startup' 3.4.18 SURVEILLANCE REQUIREMENTS SURVE!LLANCE FREQUENCY s SR 3.4.18.1 Verify cold leg temperature of isolated loop Within 30 is s [ - ]'F below the highest cold leg minutes prior temperature of the operating loops, to opening the cold log. isolation l - valve in isolated loop SR 3.4.18.2 Verify boron concentration of isolated loop - Within 2 is 2 boron concentration of the operating hours prior loops. to opening-the hot or cold leg isolation valve in isolated loop 1 CROSS-REFERENCES TITLE NUMBER Shutdown Margin 3.1.1 RCS Loop Isolation ~ Valves 3.4.17 l l WOG STS 3.4-51 06/18/90 v ,,,.v g e

4 RCS Loops - Test Exceptions 3.4.19 3.4 REACTOR COOLANT SYSTEM (RCS). 3,4.19 RCS Looos Test Exceotions L L LCO 3.4.19 The requirements of LCO 3.4.4, RCS Loops - MODES 1 AND 2' m;; l be suspended. L l -APPLICABILITY: During startup and PHYSICS TESTS with THERMAL POWER < P-7. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME- - 1 A. THERMAL POWER > P-7. A.1 Open reactor trip Immediately breakers. SURVEILLANCE REQUIREMENTS IURVEILLANCE FREQUENCY-SR 3.4.19.1 Verify THERMAL POWER is < P-7. I hour i SR 3.4.19.2 Perform ANALOG CHANNEL OPERATIONAL TEST for Within 12 each Power Range Neutron Flux--Low and hours prior Intermediate Range Neutron Flux channel and to initiation P-7. .of startup, and PHYSICS TESTS b WOG STS 3.4-52 06/18/90

g RCS Loops - Test Exceptions 3.4.19-CROSS-REFERENCES TITLE-NUMBER Reactor Trip System Instrumentation 3.3.1 Function 2.B Function 4 Function 19.B RCS Loops-MODES 1 and 2. 3.4.4-WOG STS 3.4-53 06/18/90

~ O Recirculation Loops Operating 3.4.1 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.1 Recirculation loops Operatina t LCO 3.4.1 Two recirculation loops with matched flows shall be in operation, (QB One recirculation loop may be in operation provided the following limits are made applicable: a. LCO 3.2.1, APLHGR, Single Loop Operation Lt: nits specified in the (CORE OPERATING LIMITS REPORT). b. LCO 3.2.2, MCPR, Single Loop Operation Limits specified in the (CORE OPF", TING LIMITS REPORT). c. LCO 3.3.1, RPS Instrumentation, Function 2.b of Table 3.3.1.1, Allowable Value is s ( 0.58W + 62 - 0.586W ]% ofRTP.) APPLICABILITY: MODES I and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (Requirements of the A.1 Satisfy the 24 hours LC0notmetwith]ene requirements of the recirculation loop LCO. not in operation. B. Both recirculation B.1 Be in MODE 3. 12 hours loops not in operation. QB Required Action and associated Completion Time of Condition A not met. 5Pending resolution of stability issue. BWR/4 STS 3.4-1 06/18/90 ,.e 9

Recirculation Loops Operating 3.4.1 a SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify recirculation loop jet pump flow 24 hours when mismatch is: both loops are in a. 5 [ 10 ]% of rated core flow when operation operatingat<[70)%ofratedcore flow. b. 1 [ 5 )% of rated core flow when operating at 2 [ 70 ]% of rated core

flow, t

CROSS REFERENCES TITLE NUMBER AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3.2.1 MINIMUM CRITICAL POWER RATIO 3.2.2 Reactor Protection System Instrumentation 3.3.1.1 l Reactor Coolant System Pressure and Temperature Limits 3.4.9 q l \\ BWR/4 STS 3.4-2 06/18/90 l

Jet Pumps 3.4.2 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.2 Jet Pumos LCO 3.4.2 All jet pumps shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 Be in Mode 3. 12 hours inoperable. 1 e 1 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify each jet pump satisfies criterion a

NOTE----

ot' b below for each loop with forced Only required recirculation flow: when the loop has forced a. Recirculation pump flow / speed ratio recirculation differs by 15% from normal range, flow. AND 24 hours when Jet pump loop flow / recirculation pump > 25% of RTP speed ratio differs by s 5% from the normal range, b. Each jet pump diffuser-to lower plenum differential )ressure differs by 120% from establis1ed patterns. QB Each jet pump flow differs by 110% from established patterns. BWR/4 3.4-3 06/18/90 4 ,v ,-,,,,,..,,-n.- ~. v-- +, - -., ~ - - - - - -

Jet Pumps 3.4.2 CROSS. REFERENCES - None. S BWR/4 3.4-4 06/18/90

S/RVs 3.4.3 3.4 REACTORCOOLANTSYSTEM(RCS) 4 3.4.3 Safety / Relief Valves (S/Ryi). LCO 3.4.3 The safety function of (11) S/RVs shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One :or two) A.1 Restore the 14 days S/RV :(s)) inoperable. inoperable S/RV[(s)) to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A MQ not met. B.2 Be in MODE 4. 36 hours 08 (Three) or more SRVs inoperable, t l BWR/4 3.4-5 06/18/90 . ~. k ~n..-

1 S/P.Vs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY a. SR 3.4.3.1 Demonstrate the safety function lift (Accordingto setpoints of the required S/RVs are as the Inservice follows: Testing ) Program or Number of Setpoint 18 months) ,_S/RVs fosia) '1090t10.91[ '4' 4 h 1100 t 11.0 i 3l , 1110 i ll.1.I 1 SR 3.4.3.2 Demonstrate each S/RV opens when manually 18 months actuated. i 98 12 hours when reactor steam dome pressure is 1 ( 920 ) psig CROSS-REFERENCES j TITLE NUMBER Low-Low Set Safety / Relief valves 3.6.1.8 ECCS - Operating 3.5.1 BWR/4 3.4-6 06/18/90 l

e RCS Operational Leakage 3.4.4 3.4 RiACTOR COOLANT SYSTEM (RCS) 3.4.4 M S Goerational Leakaoe 1 l LCO 3.4.4 RCS cperational LEAKAGE shall be limited to: a. No Pressure Boundary LEAKAGE, b. s 5 gpm total Unidentified LEAKAGE, ] c. 5-( 30 ) gpm Total LEAKAGE averaged over any 24 hour period, and [d. s 2 g)m increase in Unidentified LEAKAGE within any (24) lour period in MODE 1.) APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION RE0VIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce leakage to 4 hours not within limit. within limits. t B. Total LEAKAGE not B.1 Reduce leakage to 4 hours within limit, within limit. C. Unidentified LEAKAGE C.1 Verify source of 4 hours increase not within leakage increase is

limit, not service sensitive Type 304 or 316 austenitic stainless steel.

0.B C.2 Reduce leakage to 4 hours within limits. 1 (continued) l i ( BWR/4 STS 3.4-7 06/18/90 a- .s

l RCS Operational Leakage 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Actions and D.1 Be in MODE 3. 12 hours associated Completion Times not met. 680 QB D.2 Be in MODE 4. 36 hours Pressure Boundary LEAKAGE exists. SURVEILLANCE REQUIREMENTS j SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify reactor coolant system leakage is 8 hours within limits. CROSS REFERENCES TITLE NUMBER l RCS Leakage Detection Instrumentation 3.4.6 i BWR/4 STS 3.4 8 06/18/90

l RCS P!V Leakage 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) l 3.4.5 RCS Pressure Isolation Valve leakaoe l i LCO 3.4.5 The leakage from each RCS Pressuro Isolation Valve (PIV) shall be limited t0 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure 1 ( Jand s( ) psig. APPLICABILITY: MODES 1, 2, and 3. 30NS CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage from one or A.1 Restore RCS PIV 4 hours more RCS PIVs not leakage to within within limit. limit. DE A.2.1

NOTE---------

Each valve used to satisfy Required Actions A.2.1 and A.2.2 must have been demonstrated to meet SR 3.4.5.1 and be in the reactor coolant pressure boundary. l Isolate the high 4 hours pressure portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic or check-valve. NiQ l (continued) BWR/4 STS 3.4-9 06/18/90 ,-*..--r.,, ,-7-w-.- p.,

RCS PlV Leakage 3.4.5 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Isolate the high 72 hours pressure portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic or check valve. B. Required Action and B.1 Be in MODE 3. ~~ ~~ ~"12 hours ~ ~ " ~ associated Completion Time not met. MQ B.2 Be in MODE 4. 36 hours d t 4 b BWR/4 STS 3.4-10 06/18/90 L

1 RCS P!V Leakage 3.4.5 SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY l \\ l SR 3.4.5.1

NOTE-SR 3.0.4 is not applicable for entry into MODE 3 or 4 for the purpose of testing the isolation valves.

Verify leakage of each RCS PlV limited to [18 months) 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure it [ ] E ands ( ) psig. Prior to entry into MODE 2 whenever the unit has been in MODE 4 for

7. days or more if testing has not been performed in i

the previous 9 months M Within 24 hours following valve actuation due to automatic or manual action, or flow through the valve ~ CROSS REFERENCES None. I BWR/4 STS 3.4-11 .06/18/90 ..a. ,s. .....n,

RCS Leakage Detection Instrun+ntation 3.4.6 3.4 REACTOR COOLANT SYSTEM I 3.4.6 RCS Leakaae Detection Instrumentation LCO 3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE: a. Drywell floor drain sump monitoring system, and b. One channel of either Primary Containment atmospheric particulate or atmospheric gaseous montioring system, and [c. Primary Containment air coolers condensate flow rate monitoring system.] APPLICABILITY: MODES 1, 2, and 3. 7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain A.1 Restore drywell 30 days sump montioring floor drain system inoperable, monitoring system to OPERABLE status. B. Required Primary B.1 Take and analyze Oncer per 12 Containment grab sample of hours atmospheric containment monitoring system atmosphere, inoperable. [MQ B.2 Restore required 30 days ] Primary Containment atmospheric montioring system to OPERABLE status. (continued) BWR/4 STS 3.4-12 06/18/90 1

RCS Leakage Detection Instrumentation 3.4.6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME (C. Primary Containment C.1 Take and analyze Once per 12 ) air coolers grab sample of hours condensate flow rate containment mo.nitoring system atmosphere, inoperable. (D. Required Primary D.1 Restore Primary 30 days ] Containment Containment atmospheric and air atmospheric cooler condensate monitoring system to flow rate monitoring OEPRABLE status, systems inoperable. QB D.2 Restore Primary 30 days-Conatinment air cooler condensate flow rate monitoring system to OPERABLE

status, i

E. Required Actions and E.1 Be in MODE 3. 12 hours associated Completion Times not met. 68Q E.1 Be in MODE 4. 36 hours F. Two(ormore] F.1 Enter LC0 3.0.3. Immediately required leakage detection syste;ns inoperable. BWR/4 STS 3.4-13 06/18/90 r c ,e +- ,m-- -r-e.

l l RCS Leakage Detection Instrumentation i 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Perform CHANNEL CHECK of required Primary 12 hours Containment atmospheric monitoring system. SR 3.4.6.2 Perform CHANNEL FUNCTIONAL TEST of required 31 days Primary Containment atmospheric montioring sytem. 4 SR 3.4.6.3 Perfrom CHANNEL CAllBRATION of required (18 months) Primary Containment atmospheric monitoring

system, t

4 SR 3.4.6.4 Perform CHANNEL CAllBRATION of required (18 months) drywell floor drain sump monitoring system. i (SR 3.4.6.5 Perform CHANNEL CAllBRATION of required (18 months)] Primary Containment air cooler condensate flow rate monitoring system. CROSS-REFERENCES TITLE NUMBER i RCS Operational Leakage 3.4.4 i 1 Y BWR/4 STS 3.4-14 06/18/90

RCS Specific Activity 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Soecific Activity LC0 3.4.7 The specific activity of the primary coolant shall be limited to: a. $ (0.2) yC1/gm DOSE EQUIVALENT I-131, and b. A gross specific activity 5100/I gCi/gm. APPLIC.8BILITY: V10E 1, h00ES 2 and 3 with any main steam line not isolated. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary coolant A.1 Determine DOSE Once per 4 specific activity > EQUIVALENT I-131. hours [0.2) pCi/gm DOSE EQUIVALENT I-131 but E s 4.0 #Ci/gm. i A.2 Restore specific 48 hours activity to within limits. B. Required Actions and B.1 Determine DOSE Once per 4 associated Completion EQUIVALENT I-131. hours Times of Condition A not met. M 08 B.2 Isolate all main 12 hours steam lines. Primary coolant specific activity > i (4.0)#Ci/gm. C. Primary coolant C.1 Be in MODE 3 with 12 hours specjfic activity all main steam lines 100/EpCi/gm. isolated. BWR/4 STS 3.4-15 06/18/90 d

RCS Specific Activity-3.4.7 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

NOTE-------------------

Only required in MODE 1. r Demonstrate specific activity of primary 31 days coolant is s (0.2) yC1/gm DOSE EQUIVALENT I-131. SR 3.4.7.2 NOTE------------ -- --NOTE---- SR 3.0.4 is not applicable. Sample to be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since the reactor was last subcri-tical for 40 hours or + longer. Verify specific activity of the primary 184 days coolant s 100/E pCi/gm. CROSS-REFERENCES - None. t BWR/4 STS 3.4-16 06/18/90 .c

4..., --,

w-m 6

RHR. Shutdown 304.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR). Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, unless at least one recirculation pump is in operation, at least one RHR shutdown cooling subsystem shall be in operation. APPLICABILITY: MODE 3withreactorsteamdomepressure<(theRHRcut-in permissivepressure). MODE 4 ........................N0TE............................

1. Both RHR shutdown cooling subsystems may be removed from operation for up to two hours per eight-hour period provided on rubsystem is OPERABLE.

2. Both RHR shutdown cooling subsystems may be removed from operation during hydrostatic testing.

k ACTIONS CONDITION REQUIRED ACTION COMPLETION. TIME A. One required RHR A.1 Restore required RHR 8 hours shutdown cooling shutdown cooling subsystem inoperable, subsystem to OPERABLE status. QB A.2.1 Establish an 8 hours alternate method of decay heat removal. AND A.2.2 Restore required RHR 72 hours shutdown cooling subsystem to OPERABLE status. ? (continued) l BWR/4 STS 3.4-17 06/18/90 w-s ..-n., .~

RHR - Shutdown 3.4.8 ACTIONS (continued) ) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Actions and B.1 Initiate action to Immediately associated Completion restore one RHR Times of Condition A shutdown cooling not met. subsystems to OPERABLE status. E E 1 Two requires RHR shutdown cooling B.2.1 Initiate action to Immediately subsystem inoperable, establish an alternate method of decay heat removal for each inoperable subsystem. j MQ B.2.2 Restore one RHR 72 hours shutdown cooling subsystems to J OPERABLE status. C. No RHR shutdown C.1 Establish reactor 1 hour cooling coolant subsystem in circulation by an operation. alternate method. MQ C.2 Monitor reactor Once per hour coolant temperature and pressure. L BWR/4 STS 3.4-18 06/18/90 .e% ~ ,n- - - - -

RHR Shutdown 3.4.8-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify each required RHR shutdown cooling 31 days manual, power-o)erated or automatic valve in the flow path t1at is not locked, sealed or QB otherwise secured in position, can be aligned to its correct position. 12 hours when reactoi' steam 4 l dome pressure is < [the RHR cut-in I permissive i pressure) 'l CROSS REFERENCES TITLE NUMBER ECCS - Operating 3.5.1 ECCS - Shutdown 3.5.2 Residual Heat Removal Suppression Pool Cooling 3.6.2.3 Residual Heat Removal Suppression Pool Spray 3.6.2.4 BWR/4 STS 3.4 19 06/18/90

-w,

-. ~ - -., ,m-%--

RCS Pressure and Temperature Liaits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature Limits LCO 3.4.9 The combination of RCS temperature and recctor vessel pressure and RCS heatup and cooldown rates shall be maintained within limits as specified in the PRESSURE AND TEMPERATURE LIMITS REPORT. 1 APPLICABILITY: At all times. ACTIONS ) CONDITION REQUIRED ACTION COMPLETION TIME I A.

NOTE---

A.1 Restoreparameter(s) 30 minutes All Required Actions to within limits, must be completed whenever this AND Condition is entered. A.2 Determine RCS is 72 hours i Requirements of the acceptable for LCO not met. continued operation, i B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours 4 7 BWR/4 STS 3.4-20 06/18/90 i 2 ,, + - ~., -a n.. e,.

RCS Pressure and Temperature Liaits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 - ------- ------ --NOTE- --------~~----- -- Only required during system heatup, cooldown and inservice leak and hydrostatic testing. Verify RCS pressure, temperature, and heatup 30 minutes and cooldown rates are within limits. SR 3.4.9.2 Verify RCS pressure and temperature are Once within within the criticality limits. 15 minutes '~ prior to control rod withdrawal 1 for the 1 purpose of achieving j criticality SR 3.4.9.3

-- --- ---- --NOTE --------- - ----- -

Only required in MODES 1, 2, 3 and 4 (with reactor steam dome pressure 1 25 psig.) Verify the difference between the bottom Once within t head coolant temperature and the reactor 15 minutes pressure vessel coolant temperature is s prior to each (145]'F. startup of a recirculation pump l (continued) l BWR/4 STS 3.4-21 06/18/90

...:.4

+. r ~ .. ~. _

RCS Pressure and To:perature Liaits 3.4.9 E s SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.4.9.4 ..-----....---.-... NOTE-- ---------------- Only required in H0 DES 1, 2, 3 and 4. Verify the difference between the reactor Once within coolant temperature within the recirculation 15 minutes loop to be started and the reactor pressure prior to each vessel coolant temperature.is s (50]*F. startup of a recirculation pump SR 3.4.9.5 Verify the reactor vessel flange and head 12 hours when flange temperature are 2 70'F. in MODE 4 with reactor coolant system temp. erature 1 100'F. - AliQ 30 minutes when in H0DE 4 with reactor coolant system temperature s 80'F AtiQ 30 minutes when tinston-ing the reactor vessel head bolting studs l l l BWR/4 STS - 3.4-22 06/18/90 ..w- ,,,...,..r. ,,.-.r-4_. _--___.,e-,--__

RCS Pressure and Temperature Limits 3.4.9 CROSS REFERENCES TITLE NUMBER Recirculation Loops Operating 3.4.1 Inservice Leak and Hydrostatic Testing Operation 3.10.1 .~ BWR/4 STS 3.4 23 06/18/90

Reactor Stena Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Rggi.qr Steam Dome pressure LCO 3.4.10 The reactor steam dome pressure shall be s (1020) psig. APPLICABILITY: MODES I and 2, except during anticipated transients. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor 15 hours pressure not within steam dome pressure limit. to within limit. l B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 12 hours s (1020) psig, t l CROSS REFERENCES - None. BWR/4 STS 3.4-24 06/18/90 .-.f ,..n. v. ,e ,.,-,-.v, ,,.,,m.-

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loons Ooeratina LCO 3.4.1 Two recirculation loops with matched flows shall be in operation, (M One recirculation loop may be in operation provided the following limits are made applicable: a. LCO 3.2.1, APLHGR, Single Loop Operation Limits specified in the (CORE OPERATING LIMITS REPORT). b. LCO 3.2.2, MCPR, Single Loop Operation Limits specified in the (CORE OPERATING LIMITS REPORT). c. LCO 3.3.1, RPS Instrumentation, Function 2.b of Table 3.3.1.1. Allowable Value is 1 [ 0.58W + 62 - 0.58e4 ]% - ofRTP.) APPLICABILITY: MODES I and 2. ACTIONS i CONDITION REQUIRED ACTION r0MPLETION TIME l A. (Requirementsofthe A.1 Satisfy the 24 hours LC0 not met with) one requirements of-the recirculation loop LCO. not in operation. B. Both recirculation B.1 Be in M0GE 3. 12 hours loops not in operation. M Required Action and associated Completion Time of Condition A not met.

Pending resolution of stability issue.

BWR/6 STS 3.4-1 06/18/90 \\

Recirculation Loops Operating 3.4.1 0 SVRVEILLANCE RE0VIREMENTS SVRVEILLANCE FREQUENCY SR 3.4.1.1 Verify recirculation loop jet pump flow 24 hours when mismatch is: both loops are in a. 1 [ 10 ]% of rated core flow when operation operating at < [ 70 ]% of rated core flow. b. s ( 5 ]% of rated core flow when operating at 2 ( 70-)% of rated core flow. CROSS-REFERENCES TITLE NUMBER AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3.2.1 MINIMUM CRITICAL POWER RATIO 3.2.2 Reactor Protection System Instrumentation 3.3.1.1 Reactor Coolant System Pressure and Temperature Limits 3.4.9 1 e i 9 BWR/6 STS 3.4-2 06/18/90 , _,.... _ + - ~ - -

Flow Control Valves 3.4.2 4 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.2 Flow Control Valves (FCVs) LCO 3.4.2 Two recirculation loop FCVs shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two FCVs A.1 Lockup the 4 hours inoperable, inoperable FCVs. B. Required Action and-B.1 Be in MODE 3. 12 hours associated Completion Time not mat. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Demonstrate each FCV fails "as is" on loss (18 months) of hydraulic pressure at the hydraulic unit. i 1 SR 3.4.2.2 Demonstrate average rate of each FCV (18 months] movement is:- a. 1 ( 11 ]% of stroke per second for

opening, bhD b.

1 ( 11 ]% of stroke per second for closing. BWR/6 STS 3.4 3 06/18/90 v.- -me-r- ,---,-n y-

Floa Control Valves I 3.4.2 CROSS-REFERENCES - None. f 4 i e b 4 BWR/6 STS 3.5-4 06/18/90

1 Jet Pumps 3.4.3 s 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3: Jet Pumos LCO 3.4.3 All jet pumps shall be OPERABLE. APPLICABILITY: MODES 1 and 2. P ACTIONS CONDITION REQUIRED ACTION-COMPLETION TIME 1 A. One or more jet pumps A.I Be in Mode 3. 12 hours l inoperable. SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY SR 3.4.2.1 Verify each jet pump' satisfies at least two

NOTE---

1 of the following criterion (a, b, and c) in -Only required each loop with forced recirculation flow: when the loop has forced. a. Recirculation loop _ drive flow versus FCV recirculation position differs by 5 10% from flow.. established patterns. 1 b. Recirculation loop drive flow versus 24 hours when total core-flow differs by 510% from > 25%-of.RTP the normal range. c. Each jet pump diffuser-to-lower. plenum-differential pressure differs by 5 20% from established patterns. QB Each jet pump flow differs by s 10% from established patterns. l .BWR/6 3.4-5 '06/18/90

Jet Pumps-3.4.3 CROSS-REFERENCES - None. -l 4 -l I i BWR/6 3.4-6 06/18/90

S/RVs 3.4.4 3.4 REACTORCOOLANTSYSTEM(RCS)- 3.4.4 Safetv/ Relief Valves (S/RVs) LCO 3.4.4 The safety function of 1 (7) S/RVs shall be OPERABLE, AND The relief function of 2 (6) additional S/RVs shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. i 'l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME (A. One required S/RV A.1 Restore the 14 days ] inoperable, inoperable S/RV'to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time of Condition A-ANQ not met. B.2 Be in MODE 4. 36 hours i QB (One] or more required SRVs inoperable. l l 4 BWR/6 3.4-7 06/18/90-

S/RVs 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Demonstrate the safety function lift (According to setpoints of the required S/RVs are as-the Inservice follows: Testing Program or Number of Setpoint 18 months) i S/RVs fosio) ( [8) ( 1165 1 11.6 )

6)

[ 1180 1 11.8 ) [6) ( 1190 1 11.9 ) SR 3.4.4.2 Demonstrate each (required) S/RV opens when (18 months) manually actuated. ~ ~ ~ ~ ~ QB-12 hours'when reactor steam-dome pressure is 1 [ 100 ) 2 psig. s CROSS-REFERENCES TITLE-NUMBER Low-Low Set Safety / Relief valves - 3.6.1.8 ECCS - Operating 3.5.1-BWR/6 3.4-8 06/18/90:

RCS Operationai Leakage 3.4.5 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.5 RCS Operational leakaae LCO 3.4.5 RCS operational LEAKAGE shall be limited to:- a. No Pressure Boundary LEAKAGE, b, s 5 gpm total-Unidentified LEAKAGE, c. s ( 30 ) gpm Total LEAKAGE averaged over any 24-hour period, and i (d. s 2 gpm increase in Unidentified LEAKAGE within any [24]-hour period in MODE 1.] i APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION ' COMPLETION TIME l- 'A. Unidentified LEAKAGE A.1 Reduce leakage to

4. hours not within limit, within limits.

B. Total LEAKAGE not B.1 Reduce leakage to

4 hours within limit, within limit.

l l C. Unidentified LEAKAGE C.1 Verify source of' 4 hours increase not within leakage: increase is-limit. not service sensitive Type 304 or 316 austenitic stainless steel. 98 l C.2 ' Reduce leakage.to 4 hours within limits. (contiiiued) BWR/6 STS 3.4-9 06/18/90

'l RCS Operational Leakage-1 3.4.5 \\ ACTIONS j CONDITION REQUIRED ACTION COMPLETION TIME ] D. Required Actions and D.1 Be in MODE 3. 12 hours 1 associated Completion Times not met. MQ ] D,8 D.2 Be in MODE 4. 36 hours h Pressure Boundary LEAKAGE exists. SURVEILLANCE REQUIREMENTS 1 SURVEILLANCE FREQUENCY ~ r l SR 3.4.5.1 Verify reactor coolant system leakage is 8 hours within limits. CROSS-REFERENCES TITLE NUMBER RCS Leakage Detection Instrumentation 3.4.7 - 1 l. BWR/6 STS. 3.4-10 06/18/90-l l-

RCS PIV Leakage 3.4.6 3.4 _REACTORCOOLANTSYSTEM(RCS) 3.4.6 RCS Pressure Isolation Valve Leakaae l i LCO 3.4.6 The leakage from each RCS Pressure Isolation Valve (PIV) shall be limited to 0.5_gpm per nominal inch of valve size up to a maximum of 5 gpm, at a RCS pressure 2 ( ]and s[ ] psig, i e APPLICABILITY: MODES 1, 2, and 3. 1 ACTIONS ~ CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage from one or A.1 Restore RCS PIV 4 hours i more RCS PIVs not leakage to within within limit. -limit. QB -A.2.1.

NOTE----------

2 Each valve used to d satisfy Required Actions A.2.1 and A.2.2 must have'been demonstrated to meet = SR 3.4.6.1 and be in the reactor coolant pressure boundary. Isolate the high 4 hours pressure portion of_ the affected system from the low pressure portion by use of one closed manual, deactivated automatic or check valve. aHQ i (continued) BWR/6 STS 3.4-11 06/18/90

l RCS PIV Leakage-3.4.6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION: TIME A. (continued) A.2.2 Isolate the high ~ 72 hours pressure portion of' the affected system from the low pressure portion by 1 use of a second a closed manual, deactivated automatic or check valve. B. Required Action and B.1-Be in MODE 3. "~' 12 hours ~~ associated Completion Time not met. ANQ' B.2 Be in MODE 4. 36 hours t f BWR/6 STS 3.4-12 06/lB/90

l I RCS PIV Leakage 3.4.6 j. l SURVEILLANCE REQUIREMENTS' 1 [ SURVEILLANCE FREQUENCY. l SR 3.4.6.1

NOTE----------------

SR 3.0.4-is. not a)plicable for entry into . MODE 3 or 4 for tie purpose of testing the i isolation valves. j Verify leakage of each RCS PIV limited to _ (18 months) ' 0.5 gpm-per nominal inch of valve size up to j E-a maximum of 5 gpm, at a RCS pressure 2 [ ] MiQ and s [ ] psig. Prior to entry'into-MODE.2 whenever the unit has been in MODE 4 for. 7 days or-more if . testing has not been performed in j the previous l 9 months: MlD Within 24 hours. following: l valve actuation due to automatic-or manual action, or flow through the valve L L CROSS-REFERENCES - None. L BWR/6 STS-3.4-13 06/18/90

l RCS Leakage Detection Instrumentation-3.4.7 3.4 REACTOR COOLANT SYSTEM 3.4.7 RCS Leakaae Detection InstrumentatiqD LC0 3.4.7-The following RCS leakage detection instrumentation shall be OPERABLE: a. Drywell floor drain sump monitoring system, and b. One. channel lof either Primary Containment atmospheric particulate or atmospheric gaseous montioring system, and [c. Primary Containment air coolers condensate flow rate monitoring system.] APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED. ACTION COMPLETION TIME A. Drywell floor drain A.1 Restore drywell -30 days sump montioring floor drain system inoperable, monitoring-system to-OPERABLE status. B. Required Primary B.1 Take'and analyze Oncer per 12 Containment grab sample of hours i atmospheric containment monitoring system atmosphere. inoperable. [at!Q B.2 Restore' required 30 days .) Primary Containment atmospheric montioring system to OPERABLE status. (continued) BWR/6 STS 3.4-14 06/1B/90 __-,1 x ~w

I RCS Leakage Detection Instrumentati@n 3.4.7 I ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME i i C.1 Take and analyze Once per 12 ]- l- [C. Primary Containment. l air coolers grab sample of hours i condensate flow rate containment monitoring system atmosphere, inoperable.

[D Required Primary 0.1 Restore Primary 30 days:

) Containment Containment atmospheric and air atmospheric cooler condensate monitoring system to flow rate monitoring OEPRABLE status. - systems inoperable.- 98 0.2 Restore Primary 30 days Conatinment air cooler condensate-flow rate monitoring ~ system to OPERABLE status. E. Required Actions and E.1 Be in MODE 3. 12 hours associated Completion Times not met. M!Q E.1 Be in MODE 4. 36 hours' l F. Two [or more]. F.1 Enter LCO 3.0.3. Immediately required leakage detection systems inoperable. BWR/6 STS 3.4-15 06/18/90 o

t-RCS Leakage Detection Instrumentation 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform CHANNEL CHECK of required Primary 12 hours Containment atmospheric monitoring system. SR 3.4.7.2 Perform CHANNEL FUNCTIONAL TEST of. required 31 days. Primary Containment atmospheric montioring sytem. SR 3.4.7.3 Perfrom CHANNEL CALIBRATION of required [18 months] Primary Containment atmospheric monitoring system. SR 3.4.7.4 Perform CHANNEL CALIBRATION of. required- [18 months]- drywell floor drain sump monitoring system. [SR 3.4.7.5 Perform CHANNEL CALIBRATION of required- [18 months] ] Primary Containment air cooler condensate flow rate monitoring ::ystem. CROSS-REFERENCES TITLE NUMBER RCS Operational Leakage 3.4.5 BWR/6 STS 3.4-16 06/18/90 i ~ 1

RCS Specific Activity 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 1 3.4.8 RCS Soecific Activity LCO 3.4.8 The specific activity of the primary coolant shall be limited to: i a. s (0.2] pCi/gm DOSE EQUIVALENT-I-131, and b. A gross specific activity 1100/E pCi/gm. APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated. i ACTIONS CONDITION . REQUIRED ACTION COMPLETION-TIME. A. Primary coolant A.] Determine DOSE Once per 4 i specific activity > EQUIVALENT I-131. hours [0.2] #C1/gm DOSE EQUIVALENT I-131 but MQ s 4.0 #C1/gm. A.2 Restore specific 48 hours activity.to within limits. B. Required Actions and B.1 Determine DOSE Once per 4 associated Completion EQUIVALENT I-131.

hours Times of Condition A not met.

MQ' DE B.2 Isolate all main-- 12-hours steam lines. Primary coolant specific activity > (4.0] #C1/gm. ~ C. Primary coolant C.1 Be in MODE'3 with '12 hours specjfic activity > all main steam lines 100/E 'yCi/gm. isolated. t BWR/6 STS 3.4-17 06/18/90 1

RCS Specific Activity 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE . FREQUENCY-SR 3.4.8.1

NOTE-------------------

Only required in MODE 1. ? Demonstrate specific activity of primary 31 days coolant is s [0.2] #Ci/gm DOSE EQUIVALENT I-131. SR 3.4.8.2

NOTE------------~

NOTE-----

SR 3.0.4 'is. not applicable. . Sample to be; taken after a minimum of 2-EFPD and'20 days of power-operation .have elapsed-since the reactor was last subcri-tical for 48 hours or

longer, i

Verify specifig activity _of the primary ~'~ 184 days ~~ ~' ~ coolant's 100/E pCi/gm. ~- i

l CROSS-REFERENCES - None.

+w BWR/6 STS 3.4-18 06/18/90

l RHR o Shutdown 3.4.9 . 3.4 REACTOR COOLANT! SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) - Shutdown LCO 3.4.9 Two RHR shutdown cooling: subsystems shall be OPERABLE, and,- unless at least one recirculation pump Lis in operation,. at least one RHR shutdown cooling subsystem shall be in operation. APPLICABILITY: MODE 3 with reactor steam dome pressure < [the RHR cut-in permissive pressure), MODE 4 .........................N0TE------

1. Both RHR shutdown cooling subsystems may be' removed

^ from operation for up to two hours per eight-hour period provided on subsystem is.0PERABLE. ~ 2. Both RHR shutdown cooling subsystems may be removed from operation during hydrostatic testing. ACTIONS CONDITION REQUIRED' ACTION COMPLETION TIME A. One required.RHR A.1: Restore required RHR 8 hours shutdown cooling shutdown cooling subsystem inoperable. subsystem to -OPERABLE status. QB A.2.1- . Establish an-8 hours alternate method of decay heat removal. g A.2.2 Restore required RHR 72 hours shutdown cooling . subsystem to OPERABLE status. (continued)- q BWR/6 STS 3.4-19 06/18/90 1 1 I

RHR - Shutdown 3.4.9 ACTIONS (continued) s CONDITION REQUIRED ACTION COMPLETION TIME B. Required Actions and-B.1 Initiate action to Immediately associated Completion restore one RHR Times of Condition A-shutdown cooling g not met. subsystems to OPERABLE status. 08 EB Two requires RHR shutdown cooling B.2.1 Initiate action to Immediately subsystem inoperable. establish an alternate method ofidecay heat removal for each inoperable subsystem. 88D B.2.2 Restore one RHR 72 hours shutdown cooling subsystems to OPERABLE status., C. No RHR shutdown C.1 Establish reactor: I hour cooling coolant subsystem in circulation by an operation. alternate method. 83Q C.2 Monitor reactor Once per hour coolant temperature and L pressure. e BWR/6 STS 3.4-20 06/18/90 s

RHR - Shutdown - 3.4.9 I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify each required RHR shutdown cooling ,31 days. manual, power-o>erated or automatic valve in the flow path t1at is _ not locked, sealed or QB otherwise secured.in position, can,be aligned to its correct position. 12 hours when 1 reactor steam dome pressure I is <'[the RHR cut-in permissive i pressure) i CROSS-REFERENCES l TITLE NVMBER ECCS - Operating 3.5.1-ECCS - Shutdown 3.5.2 Residual Heat Removal Suppression Pool Cooling-3.6.2.3 Residual. Heat Removal Suppression' Pool Spra) 3.6;2.4 BWR/6 STS 3.4-21 06/18/90

I J RCS Pressure and Temperature Limits -I 3.4.10 1 o j L 3.4 REACTOR COOLANT SYSTEM (RCS)' 3.4.10 RCS Pressure and Temoerat'ure Limits LC0 3;4.10 The combination of RCS temperature and reactor vessel pressure and RCS heatup and cooldown rates shall be L maintained within limits as specified in the PRESSURE ANO: L TEMPERATURE LIMITS REPORT. APPLICABILITY: At all times. g - ACTIONS COMPLETION TIME CONDITION REQUIRED ACTION A.

NOTE--------

A.1 Restore parameter (s) 30 minutes All Required Actions to within;11mits. r-must be completed whenever this AND I Condition is entered. A.2 Determine RCS'is 72 hours Requirements of the acceptable for LCO not met. continued operation. i-B. Required Action and B.1 Be in M00E 3. -12 hours associated Completion Time not met. AMQ + H B.2 Be-in MODE 4. 36 hours i i r 4 4 BWR/6 STS 3.4-22 06/18/90 .+ s- -. m m ,,4

RCS Pressure and Temperature' Limits s 3~4.10 SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY SR 3.4.10.1

NOTE------------------

Only required during system heatup,- cooldown and inservice leak and hydrostatic testing. Verify RCS pressure, temperature, and heatup 30 minutes-and cooldown rates are within limits. SR 3.4.10.2 Verify RCS pressure and temperature are-Once within within the criticality limits. 15 minutes . prior to control rod withdrawal. for the purpose of achieving criticality SR 3.4.10.3

NOTE----'---------------

Only required in MODES 1, 2, 3 and 4 [with reactor. steam dome pressure 1 25 psig.) Verify the difference between th'e bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel coolant temperature. is.1 - prior to each (145] F. startup of a recirculation pump (continued)- BWR/6 STS 3.4-23 06/18/90

4. RCS Pressure and Temperature Limits 3.4.10 ~ SURVEILLANCE REQUIREMENTS (continued) SVRVEILLANCE FREQUENCY SR 3.4.10.4 ..........-...-..---N0TE------------------- Only required in MODES 1, 2, 3 and 4. ) Verify the difference between the reactor Once within coolant temperature within the recirculation 15 minutes-loop to be started and the reactor p*ressure prior to each vessel coolant temperature is s (50] F. startup of a a recirculation pump l SR 3.4.10.5 Verify the' reactor vessel flange and head 12 hours when i flange temperature are 170 F. in MODE 4 with reactor i coolant system temp-- erature < ~! 100'F M 30 minutes I when in MODE , 1 4 with reactor coolant l -_ system temperature 1 80 F M 30 minutes .when tension-ing the reactor vessel head bolting studs BWR/6 STS 3.4-24 06/18/90

RCS Pressure and Temperature Limits 3.4.10 CROSS-REFERENCES TITLE NUMBER Recirculation Loops Operating' 3.4.1. Inservice Leak and Hydrostatic Testing Operation 3.10,1 l G A t BWR/6 STS 3.4-25 06/18/90

Reactor Steam Dome Pressure 3.4.11 e 3.4-REACTOR COOLANT SYSTEM (RCS) 3.4.11 Reactor Steam Dome Pressure LCO 3.4.11 The reactor steam dome pressure shall be s (1045).psig, i APPLICABILITY: MODES I and 2, except during anticipated transients. ACTIONS CONDITION. REQUIRED ACTION CbdPLETIONTIME I A. Reactor steam dome. A.1 Restore reactor 15 hours . pressure not within ' steam dome pressure limit. to within limit. i -{ B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion i Time not met. SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY' i I SR 3.4.11.1 Verify reactor steam dome pressure is s. 12 hours [1045] psig. CROSS-REFERENCES - None. I 3 BWR/6 STS 3.4-26 06/18/90 ..}}

ML20055D963

Text

Dear Mr. Hall,

Enclosure:

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