ML20043B844

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Forwards First Draft for New STS Section 3.9, Refueling Operations, Per 900411-12 Meeting
ML20043B844
Person / Time
Issue date: 05/24/1990
From: Calvo J
Office of Nuclear Reactor Regulation
To: Hall W
NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &
References
NUDOCS 9005310382
Download: ML20043B844 (75)
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Text

{{#Wiki_filter:s k May. 24, 1990 ' v. Mr.: Warren J. Hall,' Manager Operations, Management and Support Services Division Nuclear Management and Resources Council 1776 Eye Street, Suite 300 Washington,'D.C. 20006-2496-

Dear Mr. Hall:

Enclosed is the first. draft for new STS section 3.9 Refueling. This draft incorporates the results of our meeting with NUMARC and the Owners Groups on April-11.and 12, 1990. We understand that the Owners 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 Word Perfect 5.1 by June 29, 1990. i Sincerely,- .l ORIGmAL SIGHED BY JOSE A. CALVO i Jose A. Calvo, Chief Technical Specifications Branch Division of Operational Events Assessment, NRR Enclosurt: As stated l cc:- C' DeDeaux, CE0G Chairman DISTRIBUTION: w/o Enclosure I ,J.. Hinds WOG Chairwoman TEMurley CiiBerlinger C. Sutyth, B&WOG Chairman FJMiraglia PWBaranowsky J.JJones,'BWROG Chairman WTRussell FGillespie j .E. Lozito, VEPC0 CERossi JLieberman B. Woods, SCE JGPartlow ELJordan .K. Wilson, FPC DMCrutchfield WGKennedy J. Fowler, SERI-SAVarga MGMalsch .I ( i M. Bryan, TVA CHBerlinger OTSB Members J. Jones. GPC GMHolahan OTSB R/F j ACThadani DOEA R/F q BKGrimes FJCongel JWRoe JHConran PDR W/ Enclosure gCentragfile.sfw/Enclosurewl, j / -DOCUMEllT NAME: LT HAl:L 3.9 REFUEL GILLES / +[ K3L. h, 1p*j),[p OTSB E 4~,OTSB:00EA:NRR OTSB:00EA:NRP C:0TSB:00EA:llRR JWWe FMFeinahrt RMLobel JAcalvo /YK 9 l J . '0 ', $/Lj/90 g/Li/90 s'/2y'/90 yl p M ' n ?8i E 8 E c NE ME CENTER 00Ff D R) t PDC \\ \\ t.

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p 4: to Boron Concentration 3.9.1 4 p 3.9 REFUELING OPERATIONS 3.9;1L Boron' Concentration LC0 3.9.1 Boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be . maintained within the limit specified in the COLR. APPLICABILITY:- MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE Immediately' g not within limit. ALTERATIONS. 8!!D A.2 Suspend positive Immediately reactivity additions. A!!D A.3 Initiate action to 15 minutes restore boron concentration to within limits. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration within 72 hours limit. CROSS-REFERENCES - None. i WOG STS 3.9-1 05/24/90 l

o,,, 4 L<- 5 e b'4 )! Unborated Water Source Isolation Valves S 3.9.2 -i

3. 9' REFUELING OPERATIONS a

3 ~ 9. 2 - Unborsted Water Source Isolation Valves -LC0 3 9.2-Each valve used to isolate unborated water sources shall be a secured in the closed' position.~ .............................-N0TE-- Valves may be opened.during planned boron dilution or makeup _ j activities. t APPLICABILITY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME ........N0TE-------- f Required Action A.3 -must be completed. whenever Condition A is entered. A. One or more valves A.1 Suspend CORE Immediately not secured in closed ALTERATIONS. position. AND i A.2 Initiate actions to Immediately secure valve (s) in i closed position. AdQ L A.3 Perform SR 3.9.1.1 4 hours (Boron Concentration). 4 E j l-(' -WOG STS 3.9-2 05/24/90 L 1 ', 1 l

?xy, f: W, "' w,- ic L ps og Unborated Water. Source-Isolation Valves 3.9.2 -SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY. r; .SR : 3. 9. 2.1 - Verify-each valve which isolates 31 days unborated water sources is secured in the closed position. ALD Once within I hour after. 'i a planned ' j dilution y or makeup. i 6 activity CROSS REFERENCES - None. ] t 1 t I I .j l ?j q i i i h i o

.O-I' Nuclear Instrumentation 3.9.3 3.9 - REFUELING OPERATIONS -3.9.3 -Nucl6ar' Instrumentation LCO 3. 9 '. 3 Two source range neutron flux monitors shall be OPERABLE.- APPLICABILITY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Suspend CORE 1mmediately range neutron flux ~ ALTERATIONS. monitor inoperable-. AN.D. A.2 Suspend positive-Immediately reactivity additions. BSD A.3 Initiate actions to 7 days restore source range neutron flux monitor to OPERABLE status. (continued) {. WOG STS 3.9-4 05/24/90

l

.y .l r a t. s.v Nuclear Instrumentation ~ 3.9.3 7 3 L, ACTIONS (continued) CONDITION. REQUIRED ACTION-COMPLETION TIME .l e t B. Two required source B.1 Initiate actions to' 15 minutes-. range neutron flux restore one source monitors ~ inoperable, range neutron flux monitor to OPERABLE- -[

status, E

Within 4 hours-s B.2 Perform SR 3.9.1.1 (Boron M Concentration). Once per 12 hours ~ thereafter-SVRVE!LLANCE REQUIREMENTS ' SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform -a CHANNEL CHECK. 12 hours t SR 3.9.3.2 Perform ANALOG CHANNEL OPERATIONAL TEST. 7 days 4 CROSS-REFERENCES - None. j. V i ?. L,- WOG STS 3.9-5 05/24/90 l

7 73 Ol 14 )1 ~~ Containment Penetrat' ions: 3.9.4

3. 9' REFUELING OPERATIONS h

u-g 3,9.4 Con'tainment Penetrations i LCO 3.9.4 .The containment penetrations shall be in the following- ~ status:. a. The equipment hatch closed andl held in place by'four,

bolts, o

,n: b. One door in each airlock closed, and-c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either: 1. Closed by a manual or automatic isolation 'I valve, blind flange, or equivalent, or-2. Capable of being closed by an OPERABLE - Containment Purge and Exhaust Isolation. System. . APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel.within containment. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Adjust the setpoints 4 hours required-to within limits. Containment Purge and Exhaust Isolation System U radiation channel setpoints not within limits. (continued) 1 WOG STS 3.9-6 05/24/90 t6 i

g; y n O' f - .,1 %,1 k i D t p T Containment Penetratioits-E 3.9.4 ACTIONS.(continued) CONDITION" ' REQUIRED ACTION-COMPLETION TIME s 6 B.' One or more B.1 Suspend CORE .Immediately containment ALTERATIONS. o -penetrations not-in. required: status MQ for reasons other than Condition A. B.2 Suspend movement of Immediately-fuel assemblies within QB containment. i Required Action and associated-Completion Time of .) Condition A not met. SURVEILLANCE REQUIREMENTS SVRVEILLANCE -FREQUENCY SR. 3.' 4.1 Perform a CHANNEL CHECK of each 12 hours required Containment Purge and r Exhaust Isolation System radiation channel. SR 3.9.4.2 Verify each required containment 7 days building penetration is in its required status. SR 3.9.4.3 Perform ANALOG CHANNEL OPERATIONAL 31 days TEST for each required Containment Purge and Exhaust Isolation System radiation channel. (continued) WOG STS 3.9-7 05/24/90

fsc ~4 : 7~ Containment: Penetrations 3.9.4 SVRVEILLANCE REQUIREMENTSL(continued) SURVEILLANCE FREQUENCY-SR 3.9.4.4 Perform a CHANNEL CAllBRATION of [18 months]' y each required Containment Purge and= Exhaust Isolation System radiation channel. SR 3.9.4.5 Demonstrate each required (18 months) containment purge and exhaust valve actuates to its isolation position i on (c.1] actual or simulated -l actuation signal [s), j 1 CROSS-REFERENCES - None. I d I L WOG STS 3.9-8 05/24/90

ff e -W I RHR - High Water level 3.9.5: 3.9-REFVELING.0PERATIONS 3.9.5' RYsid0al Heat Removal (RHR) and Coolant Circulation - Hiah Water Level - LC0 -3.9.5 One'RHR loop shall be OPERABLE and in operation. p i ..........................N0TE - The required RHR loop may be removed from operation for s I hour per 2-hour period, provided: a. No operations are permitted that would cause dilution of-the RCS boron concentration. APPLICABILITY: MODE' 6'with the water level 2, 23 feet above the' top of-reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION. TIME- .i A. -RHR' loop requirements A.1 Suspend' operations Immediately not met. . involving a reduction in 1 reactor coolant boron concentration. O t A.2 Suspend operations Immediately. involving an increase in reactor decay heat load. M A.3 Initiate action to 15 minutes satisfy RHR loop requirements. (Needs additional review by Owner's Group) WOG STS 3.9-9 05/24/90 )

[i ce-1, ~~ RHR --High Water Level l 3.9.5 SURVEILLANCE REQUIREMENTS s SURVEILLANCE-FREQUENCY - SR 3.9.5.1 - Verify one RHR loop in operation and '12 hours circulating reactor-coolant. h CROSS-REFERENCES TITLE NUMBER Residual Heat Removal (RHR) and Coolant _ Circulation - Low 3.9.6 Water Level I i 4 i WOG STS 3.9-10 05/24/90

rgm a i i e. h, RHR - Low Water Level 3.9.6-3.9 RE.UELING OPERATIONS r, R'sidual Heat Removal (RHR) and Coolant Circulation - Low Water 3.9.6 e level LCO 3.9.6 Two RHR loops shall be OPERABLE and one RHR loop' shall be-in. operation. l ' APPLICASILITY: h6 J 5 with the water level < 23 feet above the top of reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A'. One RHR loop' A.1 Initiate action to 15' minutes' t inoperable, restore RHR loop'to j OPERABLE status. QE A.2.1 Initiate actions to 15 minutes' establish 2 23 feet of water above the top of reactor vessel- 'l f1ange. ] 1 8NQ l A.2.2 Establish alternate

7. days decay heat removal capabilities.
  • A.2.3 Restore RHR loop to (7 days]

'l OPERABLE status. 8 ) (continued) l t i (*Resulted from review of BWRs - to be reviewed by Owner's Groep) WOG STS 3.9-11 05/24/90 t

S';; a f, E.o W ~" RHR Low Water ~ level 3.9.6' ACTIONS -(continued) CONDITIONI'- REQUIRED ACTION-COMPLETION TIME I L B.- No RHR -loop OPERABLE B.1 Suspend operations immediately l ^ or in operation.- involving a reduction in g reactor coolant boron i concentration, q AN,Q B.2'. Initiate action to. Immediately. restore one RHR loop to OPERABLE status and to operation. ANQ B.3. Initiate action to 15 minutes I implement alternate decay heat removal. i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i SR 3.9.6.1 Verify one RHR loop in operation and 12 hours circulating reactor coolant. 4 CROSS-REFERENCES TITLE NUMBER I i Residual Heat Removal and Coolant Circulation - High 3.9.5 Water Level WOG' sis 3.9-12 05/24/90 i s

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~~ Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refuelina Cavity Water level 1 LC0 3.9.7 ' Refueling cavity water level shall be maintained 123 feet above the top of reactor vessel flange. APPLICABILITY: During movement of fuel assemblies within containment with irradiated fuel in containment. ACTIONS CONDITION-REQUIRED ACTION COMPLETION TIME A. . Refueling cavity A.1 Suspend movement Immediately water level not of fuel assemblies within limit, within containment. 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE-FREQUENCY SR' 3.9.7.1 Verify refueling cavity water level 2 24 hours 23 feet-above the top of reactor vessel fl ange, m . CROSS REFERENCES TITLE NUMBER Residual Heat Removal (RHR) and Coolant Circulation - Low 3.9.6 Water Level WOG STS 3.9-13 05/24/90 i

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7-Other Refueling LCOs 3.9.8 3.9 REFUELING OPERATIONS-1 3.9.8 Other Reftelino LCOs I -- .LCO 3.9.8 All-related LCOs from other Technical Specifications (f Chapters shall be satisfied. o, APPLICABILITY: MODE 6 CHAPTERS-LCOs ] 3.1-Reactivity Control Systems None r 3.2 Power Distribution Limits None-f. 3.3 Instrumentation 3.3.2 Engineered Safety Features Actuation System-(ESFAS). Instrumentation Table - 3.3.1.1, Ba, b 3.4 Reactor Coolant System (RCS) 3.4.3 RCS Pressure and Temperature-Limits 3.4.15 Cold Overpressure' Prevention System 3.4.18 RCS Isolated Loop Startup-3.5 Emergency Core Cooling Systems None (ECCS) 3.6 Containment None 3.7 Plant Systems [3.7.13 Control Room Emergency Filtration System)- (3.7.14 Control Rn.a Emergency Air Temperature (HVAC)' System] 3.8 Electrical 3.8.2 AC Sources - Shutdown 3.8.5 DC Sources - Shutdown p 3.8.8 Distribution Systems - l' Shutdown -l (Needs additional review by Owner's Group) i I WOG STS 3.9-14 05/24/90 \\ c l l

LF I, k, 7* Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 ' Boron Concentration LCO 3.9.1 Boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR. p I APPLICABILITY: MODE 6. ACTIONS CONDITION R(QUIRED ACTION COMPLETION TIME =_ A. Boron concentration A.! Suspend CORE 1mmediately not within limit. ALTERATIONS. AND A.2 Suspend positive immediately reactivity additions. &!iD A.3 Initiate action to 15 minutes restore boron concentration to within limits, i l i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration within 72 hours limit. l y -3 .. - -~-.. ...-e - =.... - -. - - - - -

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--*--e.--,--,-*-<-w=-A-v+ i CROSS REFERENCES - None 3 CEOG STS 3.9 1 05/24/90 l I 1 i

g 31 ?... o g? ' z I~ Nuclear instrumentation 3.9.2 .3.9 REFUELING OPERATIONS v L. . 3.9.2 heleerinstrumentation g LCO 3.9.2 Two source range monitors shall be OPERABLE. APPLICABILITY: MODE 6. ACTIONS if CONDITION-REQUIRED ACTION COMPLET!ON TIME ~ b A. One required source A.1 Suspend CORE Immediately I range monitor ALTERATIONS. inoperable. AND r L L A.2 Suspend positive immediately react'ivity additions. AND i-A.3 Initiate actions to 7 days restore source range p monitor to OPERABLE

status, (continued).

t l CEOG STS 3.9 2 05/24/90 k t ! I' l_ ...)

I. o 7' Nuclear Instrumentation 3.9.2 ACTIONS _ (continued) CONDITION. REQUIRED ACTION COMPLET10N TIME B. Two required source B.1 Initiate actions to 15 minutes range monitors restore one source inoperable, range monitor to OPERABLE status. 6M0 B.2 Perform SR 3.9.1.1 Within 4 (BoronConcentration) hours AMD Once per 12 hours thereafter SURVE!LLANCE REQUIREMENTS SURVEILLANCE FRE0VENCY SR 3.9.2.1 Perform a CHANNEL CHECK. 12 hours SR 3.9.2.2 Perform CHANNEL FUNCTIONAL TEST. 7 days CROSS REFERENCES None CEOG STS 3.9 3 05/24/90 1

4 O T* Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS I i . Containment Penetrations

3. 9.3 -

LCO 3.9.3 The containment penetrations shall be in the following status: a. The equipment hatch closed and held in place by four bol ts, 4 b. One door in each airlock closed, and c. Each penetration providing direct. access from the containment atmosphere to the outside atmosphere either: .l 1. Closed by a manual or automatic isolation I valve, blind flange, or equivalent, or 2. Capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System. APPLICABILITY: During CORE ALTERATIONS, Ouring movement of irradiated fuel within containment. l ACTIONS CONDITION REQUIRED AC110N C(hPLET10N TIME i A. One or more A.1 Adjust the setpoints 4 hours required to within limits. Containment Purge and Exhaust Isolation System radiation channel setsoints not witiin limits. (continued) 1 CEOG STS 3.9 4 05/24/90 O

l j* '~ Containment Penetrations i 3.9.3 ACTIONS (continued) CONDITt0N. REQUIRED ACTION COMPLETION TIME l i B. One or more B.1 Suspend CORE 1mmediately containment ALTERATIONS. penetrations not in required status A!iQ for reasons other than Condition A. B.2 Suspend movement of Immediately fuel assemblies within QB containment. Required Action and associated i Completion Time of Condition A not r met. SURVEILLANCE REQUIREMENTS SURVE!LLANCE FREQUENCY SR 3.9.3.1 Perform a CHANNEL CHECK of each required 12 hours Containment Purge and Exhaust isolation System radiation channel. SR 3.9.3.2 Verify each required containment 7 days penetration is in its required status. SR 3.9.3.3 Perfom CHAhkEL FUNCTIONAL TEST for each 31 days required Containment Purge and Exhaust Isolation System radiation channel. (continued) CEOG STS 3.9 5 05/24/90 j 4

~] l 4 Containment Penetrations 4 3.9.3 o SVRVEILLANCE REQUIREMENTS (continued) [. SVRVEILLANCE FREQUENCY ~ SR 3.9.3.4 Perform a CHANNEL CAllBRATION of each (18 months) required Containment Purge ana Exhaust Isolation System radiation channel. 1 SR 3.9.3.5 Demonstrate each required containment (18 months) purge and exhaust valve actuates to its simulatedactuationsigna;Iactualor isolation position on (an (s). CROSS REFERENCES - None. 4 5 CEOG STS 3.96 05/24/90

r j~ SDC High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Shutdown Coolina (SDC) and Coolant Circulatiqh - Hioh Water level LCO 3.9.4 One SDC loop shall be OPERABLE and in operation. .........................N0TE The required 500 loop may be removed from operation for 11 hour per {2) hour period, provided: a. .No operations are permitted that would cause dilution of the RCS boron concentration. APPLICABILITY: MODE 6 with the water level 123 feet above the top of reactor vessel flange. ACTIONS c_ CONDITION REQUIRED ACTION COMPLETION TIME A. 500 loop requirements A.1 Suspend operations immediately not met, involving a reduction in reactor coolant boron concentration. E A.2 Suspend operations immediately involving an increase in reactor decay heat load. E A.3 Initiate action to 15 minutes satisfy SDC loop requirements. (Needs additional review by Owner's Group) CEOG STS 3.9 7 05/24/90

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Q-{t .f h "" TI SDC : High Water Level 5.9.4 9:,. +

f.,

s SURVE?,LLANCE REQUIREMENTS SURVEILLANCE-FREQUENCY (v R

SR, 3.9.4 1-Verify.one.SDC loop in operation and '

12 hours- !if ' circulating reactor coolant. ..'.,l't Y F CROSS REFERENCES l, L TITLE NUMBER F . Shutdown Cooling and Coolant Circulation ' Low' Water 3.9.5' Level > : )+ :, 4 _.g CEOG STS 3.9 8 05/24/90 - r ik J,

~ n k i l-7~ 500 Low Water Level 3.9.5 l .3.9 REFUELING OPERATIONS 3.9.5 Shutdown Coolino ($DC) and Coolant Circulation - Low Water level L LCO 3.9.5 Two SDC loops shall be OPERABLE and one SDC loop shall be in [ operation. APPLICABILITY: MODE 6 with the water level < 23 feet above the top of reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC l'oop A.1 Initiate action to 15 minutes inoperable, restore SDC loop to OPERABLE status. OE A.2.1 Initiate actions 15 minutes to establish 2 23 feet of water i above the top of reactor vessel flange. AND A.2.2 Establish 7 days alternate decay heat removal capabilities AND

  • A.2.3 Restore SDC loop (7 days) to OPERABLE status.

(continued) (*Resulted from review of BWRs to be reviewed by Owner's Group) CEOG STS 3.9 9 05/24/90 1 l l l

= 1 s SDC Low Water Level-o 3.9.5 ACTIONS (continued) CONDITION. REQUIRED ACTION COMPLET10N TIME B. No 500 loop OPERABLE B.1 Suspend operations immediately or in operation. involving a reduction in boron concentration. 6!iD B.2 Initiate action to immediately restore one SDC loop to OPERABLE status and to operation. 8!iD B.3 initiate action to 15 minutes implement alternate decay heat removal. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one SDC loop in operation and 12 hours circulating reactor coolant. CROSS REFERENCES ~ TITLE NUMBER Shutdown Cooling and Coolant Circulation - High Water 3.9.4 Level CEOG STS 3.9 10 05/24/90

a O \\ Refueling Water Level 3.9.6 3,9 REFUELING OPERATIONS 3.9.6 Refuelina Water Level l LCO 3.9.6 Refueling water level.shall be maintained 123 feet above the top of reactor vessel flange. APPLICABILITY: During movement of fuel assemblies within containment wit!. irradiated fuel in containment. ACTIONS i CONDITION REQUIRED ACTION COMPLET!ON TIME A. Refueling water level A.1 Suspend movement immediately not within limit, of fuel assemblies within containment. SVRVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling water level 123 feet 24 hours l above the top of reactor vessel flange. CROSS REFERENCES l TITLE NUMBER i SDC Low Water Level 3.9.5 CE0G STS 3.9 11 05/24/90

Y Other Refueling LCOs 3.9.7 3.9 REFUEllNG OPERATIONS 3.9.7 0ther Refuelina LCOs LCO 3.9.7 All related LCOs from other Technical Specifications Chapters shall.be satisfied. APPLICABillTY: MODE 6. O CHAPTERS LCOs 3.1 Reactivity Control Systems None 3.2 Power Distribution Limits None 3.3 Instrumentation 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation Table 3.3.2; Ciii, di, dii, 74, 7b, 7c, 10a, lla d 3.4 Reactor Coolant System (RCS) 3.4.3 RCS Pressure and Temperature Limits 3.4.16 Low Temperature Overpressure Protection Systems { i 3.5 Emergency Core Cooling System None I (ECCS) 3.6 Containment None 3.7 Plant Systems L3.7.12 CREACS1

3.7.13 Control Room Emergency Air Temperature (HVAC)' System) 3.8 Electrical 3.8.2 AC Sources Shutdown 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems -

Shutdown (Needs additional review by Owner's Group) CEOG STS 3.9-12 05/24/90 1 l

Ts l 0 '~ Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 ' Boron Concentration LCO 3.9.1 Boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR. APPLICABillTY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE 1mmediately not within limit. ALTERATIONS. A!iQ A.2 Suspend positive immediately reactivity additions. AND A.3 Initiate action to 15 minutes restore boron concentration to within limits. I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration within limit. 72 hours CROSS REFERENCES - None B&W STS 3.9 1 05/24/90

$'i O ' ' ii Nuclear Instrumentation 3.9.2 3.9- 'REFUEllNG OPERATIONS 3.9.2 Nuclear Instrumentation

LCO-3.9.2 Two source range neutron flux monitors shall be OPERABLE.

i: APPLICABILITY: MODE 6. ACTIONS F CONDITION. REQUIRED ACTION COMPLETION TIME o t A. One required' source A.) Suspend CORE Immediately range neutron flux ALTERATIONS. monitor inoperable. M A.2 Suspend positive immediately reactivity additions. E A.3 initiate actions to 7 days restore source range neutron flux monitor to OPERABLE status. (continued) B&W STS 3.9 2 05/24/90 e J s --r, y ,y e

0' d Nuclear Instrumentation 1 L 3.9.2 i L ACTIONS (continued) CONDITION - REQUIRED ACTION COMPLETION TIME B. Two required source B.1 Initiate actions to 15 minutes L range neutron flux restore one source i monitors inoperable, range neutron flux monitor to OPERABLE status. E B.2 Perform SR 3.9.1.1 Within 4 (BoronConcentration) hours M Once per 12 hours thereafter SURVEllLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1 l-SR 3.9.2.1 Perform a CHANNEL CHECK. 12 hours l l SR 3.9.2.2 Perform CHANNEL FUNCTIONAL TEST. 7 days t CROSS REFERENCES None. B&W STS 3.9 3 05/24/90 A

I e Containment Penetrations 3 3.9.3 i 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations 1 LCO 3.9.3 The containment penetrations shall be in the following status: i a. The equipment hatch closed and held in place by four bolts, b. One door in each airlock closed, and c. Each penetration providing direct access from the containment atmosphere to the outside i atmosphere either: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2. Capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation l System. ~ APPLICABILITY: During CORE ALTERATIONS, Ouring movement of irradiated fuel within containment. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A,1 Adjustthesetpoints 4 hours required to within limits. Containment Purge and Exhaust isolation System radiation channel set 00ints not wit 11n limits. (continued) B&W STS 3.9-4 05/24/90

e i, t I' Containment Penetrations 3.9.3 ACTIONS (continued)' i-C ONDIT !DN.' ' REQUIRED ACTION COMPLETION 11ME B. One or more B.1 Suspend CORE 1mmediately containment ALTERATIONS. p-penetrations not ~ in required status &!iD for reasons other than Condition A. B.2 Suspend movement of immediately fuel assemblies Q3 within containment. Required Action and associated Completion Time of Condition A not met. SURVEILLANCE REQUIREMENTS SURVE!LLANCE FREQUENCY q SR 3.9.3.1 Perform-a CHANNEL CHECK of each required 12 hours Containment Purge and Exhaust 1 solation System radiation channel. SR 3.9.3.2 Verify each required containment 7 days penetration is in its required status. SR 3.9.3.3 Perform (CHANNEL FUNCTIONAL TEST) for 31 days each required Containment Purge and Exhaust Isolation System radiation channel. (continued) B&W STS 3.9 5 0$/24/90 i

F.i J o t Containment Penetrations 3.9.3 L SURVE!LLANCE REQUIREMENTS (continued) SURVE!LLANCE FREQUENCY SR 3.9.3.4 Perform a CHANNEL CAllBRATION of each (18 months) i-required Containment Purge and Exhaust Isolation System radiation channel. 1 SR 3.9.3.5 Demonstrateeach(required) containment (18 months) purge and exhaust valve actuates to its isolation position on (an) actual or simulatedactuationsignal(s). CROSS REFERENCES + None 6 Y k B&W STS 3.9 6 05/24/90

s sl 7'

DHR High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Decay Heat Removal (DHR) and Coolant Circulation. Hioh Water ,evel. LCO 3.9.4 One DHR loop shall be OPERABLE and in operation. .........................N0TE.............................. The DHR pump of the DHR loop in operation may be de-energized for s 8 hours per 24 hour period, provided: a. No operations are permitted that would cause dilution of the RCS boron concentration, and b. Core outlet temperature is maintained at <200'F. APPLICABILITY: MODE 6 with the water level 2 23 feet above the top of the reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DHR loop requirements A.1 Suspend operations Immediately not met, involving a reduction in reactor coolant boron concentration. M y A.2 Suspend operations immediately involving an increase in reactor decay heat load. M A.3 Initiate action to 15 minutes satisfy DHR loop requirements. (Needs additional review by Owner's Group) B&W STS 3.9 7 05/24/90 I

e 1 f e-7~ OHR - High Water Level 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY L SR 3.9.4.1 Verify core outlet temperature < 200*F. 12 hours SR 3.9.4.2 Verify one OHR loop in operation and 12 hours circulating reactor coolant. SR 3.9.4.3 Perform a CHANNEL CHECK for Core Exit 31 days Thermocouples. SR 3.9.4.4 Perform CHANNEL CALIBRATION for Core 18 months Exit Thermocouples i CROSS REFERENCES TITLE NUMBER Decay Heat Removal (OHR) and Coolant Circulation - Low 3.9.S Water Level I 4 B&W STS 3.9 8 05/24/90 i l..

i s 4 l 7~ DHR Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 'Decav' Heat Removal (DHR) and Coolant Circulation Low Water Lt3.t1 LCO 3.9.5 Two OHR loops shall be OPERABLE and one OHR loop shall be in operation. - APPLICABILITY: MODE 6 with the water level < 23 feet above the top of reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DHR loop A.1 Initiate action to immediately inoperable, restore DHR loop to OPERABLE status. QB A.2.1 Initiate actions to 15 minutes establish 2 23 feet of water above the i top of reactor vessel flange. AND A.2.2 Establish alternate 7 days decay heat removal capabilities. 880

  • A.2.3 Restore DHR loop to (7 days)

OPERABLE status. (continued)' (*Resulted from review of BWRs to be reviewed by Owner's Group.) B&W STS 3.9 9 05/24/90 S l

l' y ~^ DHR - Low Water Level 3.9.5' ACTIONS (continued) CONDITION. REQUIRED ACTION. COMPLETION 11ME ^ B. No DHR loop OPERABLE B.1 Suspend operations immediately or in operation, involving a reduction in reactor coolant boron concentration. O r B.2 Initiate action to Imr:,ediately restore one DHR loop to OPERABLE status and to operation. B.3 Initiate action to 15 minutes implement alternate decay heat removal. SURVEILLANCE REQUIREMENTS SURVEll1ANCE FREQUENCY SR 3.9.5.1 Verify one DHR loop in operation and 12 hours circulating reactor coolant. CROSS REFERENCES TITLE NUMBER 1 DHR High Water Level 3.9.4 B&W STS 3.9 10 05/24/90 e m_

Fj t ~~ Refueling Canal Water level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 ,Refuelina Canal Water Level LCO 3.9.6 Refueling canal water level shall be maintained 2 23 feet above the top of reactor vessel flange. APPLICABILITY: During movement of fuel assemblies within containment with irradiated fuel in containment. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling canal water A.1 Suspend movement. Immediately level not within of fuel assemblies limit. within containment. SURVEILLANCE REQUIREMENTS j SURVE!LLANCE FREQUENCY j SR - 3.9.6.1 Verify refueling canal water level 2 23 24 hours feet above the top of reactor vessel fl ange. -j CROSS REFERENCES TITLE NUMBER 1 DHR - Low Water Level 3.9.5 i i I B&W STS 3.9 11 05/24/90 i 1 l

0; a

'~ Other Refueling LCOs 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Other Refuelina LCOs LCO 3.9.7 All related LCOs from other Technical Specifications Chapters shall be satisfied. APPLICABILITY: MODE 6-CHAPTERS LCOs 3.1 Reactivity Control Systems None 3.2 Power Distribution Limits None 3.3 Instrumentation None 3.4 Reactor Coolant System (RCS) 3.4.3 RCS Pressure and Temperature limits 3.4.15 Low Temperature Overpressurization Protection Systems 3.5 Emergency Core tooling Systems None (ECCS) 3.6 Containment None 3.7 Plant Systems 1:3.7.12 CREACS) ?3.7.13 Control Room Emergency Air Temperature (HVAC) System) 3.8 Electrical 3.8.2 AC Sources Shutdown 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown l (Needs additional review by Owner's Group) B&W STS 3.9 12 05/24/90 i I

i Refueling Equipment Interlocks i 3.9.1 3.9 REFUEllEG:DPERATIONS t 3.9.1 Refuelina EcuiDment Interlocks 1 LCO 3.9.1 .The Refueling Equipment Interlocks shall be OPERABLE. ] 1 APPLICABILITY: During CORE ALTERATIONS involving handling fuel assemblies with equipment associated with the interlocks. I ACTIONS J CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend CORE Immediately required Refueling ALTERATIONS involving Equipment Interlocks handling fuel inoperable. assemblies with equipment associated with the inoperable interlock (s). SURVEILLANCE REQUIREMENTS SURVEILLANCE FRE0VENCY SR 3.9.1.1 Perform a Refueling Equipment Interlock 7 days l CHANNEL FUNCTIONAL TEST on each of the following required inputs: A. All rods in. t B. Refuel platform position. C. Refuel platform (main) hoist, fuel-loaded. 1 l l BWR/6 STS 3.9-1 05/24/90 I L l

0 ' g.. j ,1 'i ' j'/E . Refueling Equipment Interlocks Q g. ~ 3.9.1 CROSS REFERENCIL i TITLE NUMBER G-Single' Control Rod Drive, Removal -' Refueling 3.16.5 ) r I I i l .n j j o t a i 1 'l I I i i W i BWR/6 STS 3,9 2 05/24/90-f .1 +. -. 1 .i- - - - -

a Refuel Position One-Rod Out Interlock p

3.9.2 3.9 REFUELING:0PERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock p LCO 3.9.2 .The Refuel position one rod out interlock shall be OPERABLE. APPLICABILITY: MODE 5 with the Reactor Mode Switch in the Refuel position and any control rod withdrawn. s h ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one. A.1 Suspend control rod Immediately rod-out interlock withdrawal. inoperable. hM ( A.2 Initiate action to immediately [ fully insert all insertable control rods in core cells containing one or more fuel assemblies. M SURVEILLANCE REQUIREMENTS SURVEILLANCE FRE0VENCY SR 3.9.2.1 Perform a CHANNEL FUNCTIONAL TEST. 7 days QB 1 hour when any control rod is withdrawn BWR/6 STS 3.9 3 05/24/90 m m

f Refuel Position One Rod Out Interlock [ 3.9.2 CROSS. REFERENCES. 'i TITLE NUMBER Single Control Rod Withdrawal - Hot Shutdown 3.10.3 Single Control Rod Withdrawal Cold Shutdown 3.10.4 Single Control' Rod O' rive Removal Refueling 3.10.5 t l 1 f I b I, i 6 V 3 BWR/6 STS 3.9 4 05/24/90 1

x

g. f

,[} a-Control Rod-Position h '3.9.3 p o-3.9. REFUEL!!iG DPERATIONS-p 3.9.3 Cbntrol Rod Position LCO -3.9.3 All control rods shall be fully inserted. ~ F APPLICABillTY:~ When loading fuel assemblies 'into the core, and (not following an' approved spiral reload sequence). ACTIONS CONDITION REQUIRED ACTION COMPLETION-TIME A.- One or more control A.1 Suspend loading fuel Immediately. rods not fully assemblies into the

inserted, core.

i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY .SR 3.9.3.'l Verify all control rods are fully inserted. 12 hours CROSS REFERENCES - None. i ? BWR/6 STS 3.9-5 05/24/90 i 3 2 a

.s Control Rod Position Indication. ~ ./~ 3. 9.' 4 3.9 ' REFUEllE SPM 'ONS ' 3.9.4 'Gh0#plJtthsit1onIndication LCO 3.9.4-One ontrol rod (Full In) position indicator for each c,ontrol rod shall be OPERABLE. . APPLICABILITY: MODE 5. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.l.1 Suspend CORE. Imediately position indicators ALTERATIONS inoperable. A.I.2 Suspend control rod Imediately l withdrawal E A.l.3 Initiate action to. Imediately l i. fully insert all -i insertable control I rods. DE A.2.1 Initiate. action to imediately fully insert the control rod (s) associated with the inoperable. position 1 indicator j m ) A.2.2 . Initiate action to imediately I disarm the associated fully inserted control rod drive (s). i -BWR/6 STS 3.9-6 05/24/90

Control Rod Position Indication 3.9.4 SURVEILLANCE RE0TUIREMENTS SURVEILLANCE FRE0VENCY SR '3.9.4;l Verify each required control rod (Full In). 24 ho'urs pos'i. tion indicator is OPERABLE. j l i CROSS REFERENCES TITLE NUMBER Refueling Equipment Interlocks

3. 9.1 -

Refuel Position One Rod Out Interlock-3.9.2 Single' Control Rod Withdrawal Hot Shutdown 3.10.3 Single Control Rod Withdrawal Cold Shutdown 3.10.4 Single Control Rod Drive Removal Refueling 3.10.5' s , BWR/6 STS 3.9-7 05/24/90 ~ --

j Control Rod OPERABILITY Refueling-v. 3.9.5 [ gf -3.9 REFUELING OPERATIONS 3.9.5 Cont'rol Rod OPERABILITY - Refuelina J LCO 3.9.5 All withdrawn control rods.sht411 be OPERABLE. i APPLICABILITY: MODE 5. i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more with-A.I.1-Initiate action to immediately drawn control rods fully insert inoperable, inoperable withdrawn control rod (s). SURVEILLANT'E REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Demonstrate that each withdrawn control rod 7 days will insert at least one notch. i SR.3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 1 [ 940 ) psig. 1 CROSS-REFERENCES TITLE NUMBER 1 Single Control Rod Withdrawal - Hot Shutdown 3.10.3 Single Control Rod Withdrawal - Cold Shutdown 3.10.4 Single -Control Rod Removal Refueling 3.10.5 BWR/6 STS 3.9-8 05/24/90

',--i '(RPV) Water Level-j 3.9.6-3 '. 9 REFUELIRG' OPERATIONS i e 3.9.6 TReactor Pressure Vessel (RPVjl Water Level i LCO ~3.9.6 .[ Reactor Pressure Vessel (RPV)) water level shall i .be 1 ( 23 ) feet above the top of the RPV flange. APPLICABILITY: When handling irradiated fuel assemblies over or within the RPV. When handling fuel assemblies over or within the RPV with irradiated fuel assemblies seated within the RPV. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (RPV) water level not A.1 Suspend handling fuel Immediately i within limit, assemblies over or within the RPV. i SURVEILLANCE REQUIREMENTS L SURVEILLANCE FREQUENCY SR. 3.9.6.1 Verify (RPV) water level is 1 [ 23 ) feet 24 hours above the top of the (RPV flange). CROSS-REFERENCES TITLE NUMBER ECCS - Shutdown 3.5.2' >t i Residual Heat Removal - High Water Level 3.9.7 Residual Heat Removal - Low Water Level 3.9.8 l i 1 L BWR/6 STS 3.9 9 05/24/90 L 9

. v RHR - High dater Level, 3.9.7-3.9-REFUELIEG GPERATIONS' 3.9.7 Residual Heat Removal (RHR) - Hiah Water Level c4

-LCO 3.9.7 One Residual Heat Removal (RHR) shutdown cooling subsystem shall' be OPERABLE. APPLICABILITY: MODE 5 with water level 2 ( 23.] feet above the top of the RPV flange. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR shutdown cooling A.1 Initiate action to 15 minutes subsystem inoperable, restore RHR shutdown cooling subsystem to OPERABLE status. QB A.2.1 Initiate' action to immediately establish an alternate method of decay heat removal. 88D A.2.2 Restore RHR shutdown [72 hours] cooling sobsystem to OPERABLE status, gontinued) BWR/6 STS-3.9-10 05/24/90

(;ll s RHR' High Water Level 3.9.7 -,2 ACTIONS (cont +nued) CONDITION ~ REQOIRED ACTION COMPLETION TIME -B. Required.' Action and' B1 initiate action to immediately associated.Compi.etion provide an alternate-of Condition.A n'ot' method of decay heat met. removal. E 4 B.2 Suspend operations immediately involving an increase in reactor: decay heat load.- E B.3 Initiate action to I hour restore Secondary Containment to OPERABLE status. E B.4 Initiate' action to I hour restore one SGTS subsystem to OPERABLE status. E 1 hour B5 Initiate action to restore one. Secondary Containment Isolation Valve and associated instrumentation to OPERABLE status in each-associated penetration not isolated. BWR/6 STS 3.9 11 05/24/90

k RHR - High Water Level " ir 3.9_7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY . SR ' 3.9.8.1 Verify-that each required valve in the RHR 7 days shutdown cooling subsystem flow path is in its correct position or can be aligned to its correct position. a -CROSS REFERENCES -TITLE NUMBER .l Secondary Containment Isolation Actuation Instrumentation' 3.3.6.2 l ECCS - Shutdown 3.5.2 1 Secondary Containment - Operating 3.6.4.1.1 Secondary Containment Isolation ~ Valves Operating 3.6.4.2.1 Standby Gas Treatment System 3.6.4.3 1 4 BWR/6 STS 3.9-12 05/24/90

t RHR Loc dater Level' 3.9.8 3.9 REFUEllhGlbPERATIONS 3.9.8l Residual Heat Removal (RHR) - Low Water level 'LCO 3.9.8 .Two Residual Heat Removal (RHR) shutdown cooling subsystems .shall be OPERABLE. ~ APPLICABillTY: MODE 5 with water level < (' 231 feet above the top of the RPV flange. ACTIONS CONDITION-REQUIRED ACTION COMPLET10N' TIME 'A. One RHR shutdown A.1 Initiate action to 15 minutes cooling subsystem _ restore RHR shutdown inoperable, cooling subsystem to OPERABLE status. QB A.2.1 Initiate action to 15 minutes establish a ( 23 ) feet of water above the top of reactor vessel flange. AllD A.2.2 Establish alternate 7' days decay heat removal capabilities. 8HQ A.2.3 Restore RHR shutdown ~(7 days) cooling subsystem to OPERABLE status. (continued) e BWR/6 STS 3.9 13 05/24/90 i l 1 i e--ew

y!1 4 r . ::( : 1 qs RHR1-.-Lod Water Level ,3.9 B" j.,; . ACTIONS (continued) CONDITION' REQUIRED ACTION. -COMPLET10N-TIME -B. 'Both RHR shutdown B.1 Initiate action to immediately ~ cooling subsystems restore one RHR inoperable, shutdown cooling subsystem to OPERABLE status. QB B.2.1 Initiate action to immediately establish alternate decay heat' removal capabilities. 8.!iD 'B.2,2 Restore one RHR .[72 hours) shutdown cooling subsystem to OPERABLE status. (continued)- 8 BWR/6 STS 3.9 14 05/24/90 I 't

.,z, 3 RHR -: Low Water Level-z 't" 3.9.8 q ACTIONS (continued) -CONDITION REQUIRED ACTION ~ COMPLETION-TIME .l

=-

C. Required Action and-C. l' Initiate action to immediately .a associated'Co'mpletion provide an alternate Time not met.' . method of decay heat -removal.- 9 O o C.2 ' Suspend operations C involving an increase immediately in reactor decay heat load. A!!Q + C.3-Initiate action to restore Secondary I hour Containment to OPERABLE' status. l 6!!D C.4 -Initiate action to-restore one SGTS I hour subsystem to OPERABLE -status, i g C.5 Initiate action to restore one Secondary 1 hour

j Containment ' Isol ation -

Valve and associated instrumentation to i OPERABLE status in-each associated penetration not. 1 isolated. i i g-. BWR/6 STS 3.9-15 05/24/90

_n- =

  • RHR Loa dater Level 3.9.8-SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify that each required valve in the RHR 7 days shutdown cooling subsystem flow path is in its correct' position or.can be aligned to ~ 'its correct position. I SR 3.9.8.2 . Verify one RHR shutdown cooling subsystem in opeation and circulating reactor coolant. 1 i I CROSS-REFERENCES 4 TITLE NUMBER-Secondary Containment Isolation Actuation Instrumentation 3.3.6.2 ECCS - Shutdown 3.5.2 Secondary Containment - Operating 3.6.4.1.1 Secondary Containment Isolation Valves 3.6.4.2.1 -q Standby Gas Treatment System 3.6.4.3 4 i i i

  • BWR/6 STS 3.9-16 05/24/90

r. 1 ~, R'.' t.u -Other Refueling LCOs f. ;- 3.9.9 3.9-REFUELING OPERATIONS 3.9.9 Other'Refuelina LCOs LCO-3.9.9L All related LCOs from other Technical Specifications C.hapters shall be satisfied.' ~ ~ APPLICABILITY: MODE 5 CHAPTERS LCO'S-3.1 Reactivity Control Systems 3.1.1 -Shutdown Margin 3.2 Power Distribution Limits None 3.'3 Instrumentation 3.3.1.1 Reactor Protection System-Instrumentation Table 3.3.1.1; la, lb, 2a, 2e,_8b,. 11, 12, 13 3.3.1.3 Reactor Protection System Shorting Links 3.3.5.1 ECCS Actuation Instrumentation Table 3.3.5.1; la, Ic, Id, le, If, 2a, 2c-1, 3h, 41, Si 3.3.6.1 ' Primary Containment -1 solation Actuation Instrumentation _ Table 3.3.6.1; 6b, 6c 3.3.7.1 Main Control Room Environmental Control System Actuation Instrumentation Table 3.3.7.1; 1, 5, 6, 7 3.3.8.1 Loss of Power Instrumentation 3.3.8.2 Reactor Protection System Electric Power Monitoring . BWR/6 STS 3.9-1 05/24/90 i i..

, ;ii Other Refueling LCOs ,j '. - 3.9.9-CHAPTERS LCO'S 3.4 Reactor. Coolant System (RCS) 3.4.9 RCS Pressure and Temperature Limits x. 3.5 Emergency Core Cooling System 3.5.2 ECCS-Shutdown / (ECCS) 3.6 Contat.nment 3.6.1.3 Primary Containment Isolation Valves 3.7 Plant Systems 3.7.5 Main Control Room Environmental-Control System 3.7.6 Control Room Emergency Air. Temperature Control (HVAC) System '3.8 Electrical 3.8.2 AC Sources - Shutdown 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (Needs additional review by Owner's Group) BWR/6 STS 3.9-2 05/24/90

'J Un

/

Refueling Equipment Interlocks-3.9.1 3.9 REFUELING OPERATIONS 3.9.1-Refuelina Eauipment Interlocks LCO 3.9.1 The. Refueling Equipment Interlocks shall'be OPERABLE. APPLICABILITY: During CORE ALTERATIONS involving handling fuel assemblies with equipment associated with the interlocks. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend CORE-Immediately required Refueling. ALTERATIONS involving Equipment Interlocks handling - fuel inoperable, assemblies with equipment associated with the inoperable interlock (s). SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform a Refueling Equipment Interlock 7 days CHANNEL FUNCTIONAL TEST on each of the following required inputs: A. All-ro'ds-in. B. Refuel platform position. C. Refuel platform [ fuel grapple), fuel-loaded. [ D. Frame mounted hoist, fuel-loaded.] [ E. Monorail mounted hoist, fuel-loaded.] [ F. Fuel grapple position. ] [ G. Service Platform hoist, fuel-loaded ] . BWR/4 STS 3.9-1 05/24/90 i

c,; ~~' Refueling Equlpment Interlocks-3.9.1' CROSS-REFERENCES TITLE NUMBER Single Control Rod Drive Removal - Refueling 3.10.5 I BWR/4 STS 3.9-2 05/24/90 l s

'= Refuel Position One-Rod Out Interlock o 3.9.2 3.9 REFUELINGpPERATIONS 3.9.2 Refuel Position one Rod-out Interlock e-LCO: 3.9.2' ,The Refuel position one-rod out interlock shall be OPERABLE. APPLICABILITY: MODE 5 with the Reactor Mode Switch in the Refuel position and any control rod withdrawn. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-A.1 Suspend control rod immediately rod-out interlock withdrawal. inoperable. LLD A.2 Initiate action to immediately fully insert all insertable control rods in core cells containing one or-more fuel assemblies. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i .SR 3.9.2.1 Perform a CHANNEL FUNCTIONAL TEST. 7' days gg 1 1 hour when i any control i rod is withdrawn BWR/4 STS 3.9-3 05/24/90 l

i: Refuel Position' One-Rod Out Interlock-9J 3.9.2. CROSS REFERENCES-TITLE NUMBER Single Control Rod Withdrawal - Hot Shutdown 3.10.3 4 Single' Control Rod Withdrawal - Cold Shutdown-3.10.4 Single Control Rod Drive Removal - Refueling 3.10.5 1 i 2 1 i i 1 h 4 j :, j l p 5 4 i BWR/4 STS 3.9-4 05/24/90 L

l.'. Control Rod Position 3.9.3' 3.9 REFUELING 0PERATIONS-3.9.3 Control Rod PositioD' LCO 3.9.3 ,All control rods shall be fully inserted. APPLICABILITY: .When loading fuel assemblies-into the core, and (not following an approved spiral' reload sequence). ACTIONS REQUIREDkCTON CONDITION COMPLETION TIME

14. One or more control A.1 Suspend loading fuel Immediately rods not fully assemblies into the
inserted, core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 . Verify all control ' rods are fully inserted. 12 hours CROSS REFERENCES - None BWR/4 STS 3.9-5 05/24/90

.c..: Control Rod Position Indication-o p3 3.9.4' I 3.9. REFUELING OPERATIONS, 3.9.4-Control Rod Position Indication ~.9.4 All control rod (Full In) position indicators shall be LCO 3 OPERABLE. l APPLICABILITY: MODE 5. l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.I.1 Suspend CORE Immediately position indicators ALTERATIONS inoperable. i O l A.I.2 Suspend control rod immediately withdrawal 9 l A.l.3 Initiate action to immediately fully insert all 1 insertable control rods. A.2.1 Initiate action to immediately fully insert the. control rod (s) associated with the inoperable position indicator E A.2.2 Initiate action to Immediately disarm the associated fully inserted control rod drive (s). BWR/4 STS 3.9-6 05/24/90 1

.c Control Rod Position Indication - W-3.9.4 SURVEILLANCE-REQUIREMENTS SURVEILLANCE FRE0VENCY j SR 3.9.4.1 Verify each required control rod (Full In) 24 hours position indicator is OPERABLE. j i CROSS. REFERENCES l TITLE NUMBER Refueling Equipment Interlocks 3.9.1 Refuel Position One Rod-Out Interlock 3.9.2 l Single Control Rod Withdrawal - Hot Shutdown 3.10.3 q o Single' Control Rod Withdrawal - Cold Shutdown 3.10.4 Single Control Rod Drive Removal - Refueling 3.10.5 l 1 t i I i i 1 BWR/4 STS 3.9-7 05/24/90

},. y o Control Rod OPERABILITY'- Refueling-3.9.5 -- l 3.9 REFUELING' OPERATIONS 3.9.5 ' Control Rod OPERABILITY - Rcfuelina I LCO 3.9.5 'All withdrawn control rods shall be 0PERABLE. l APPLICABILITY: MODE 5. l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. One or more with-A.I.1 Initiate action to immediately i drawn control rods fully insert i inoperable. inoperable withdrawn j control rod (s). i SURVEILLANCE REQUIREMENTS 4 SURVEILLANCE FREQUENCY i .SR-3.9.5.1 Demonstrate that each withdrawn control rod 7 days l will insert at least one notch. 'i SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 1 [ 940 ) psig. i CROSS-REFERENCES TITLE NUMBER Single Control Rod Withdrawal - Hot Shutdown 3.10.3 Single Control Rod Withdrawal - Cold Shutdown 3.10.4 Single Control Rod Removal - Refueling 3.10.5

  • BWR/4 STS 3.9-8 05/24/90 l

.'i [RPV)' Water' Level at 3.9.6-

"" a 3.9
, REFUELING OPERATIONS-

~ 3.9.6 IReactor Pressure Vessel (RPV)1 Water Level LCO 3.9.6 (Reactor' Pressure Vessel (RPV)] water level shall be 4 [ 23 ) feet above the top of the RPV flange. APPLICABIllTY: When handling irradiated fuel assemblies over or within the RPV. When handling fuel assemblies over or within the RPV with irradiated fuel assemblies seated within the RPV. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (RPV) water level not A.1 Suspend handling fuel Immediately-within limit, assemblies over or within the RPV. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR-3.9.6.1 -Verify (RPV) water level is 2 ( 23 ] feet 24 hours above the' top of the (RPV flange]. CROSS-REFERENCES TITLE NUMBER ECCS - Shutdown 3.5.2 Residual Heat Removal - High Water Level 3.9.7 Residual Heat Removal - Low Water Level 3.9.8 BWR/4 STS 3.9-9 05/24/90

4 'l. RHR High Water Level 3.9.7 3.9 .REFUELINGpPERATIONS 3.9.7: Residual Heat Removal (RHR) - Hioh Water level LCO 3.9.7 ,0ne Residual Heat Removal (RHR) shutdown cooling subsystem-shall: be OPERABLE. APPLICABILITY: MODE 5 with water level 1 [ 23 ) feet above the top of'the RPV flange. ) a - ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1 . A. RHR shutdown cooling A.1 Initiate action to 15 minutes-subsystem inoperable. restore RHR shutdown t cooling subsystem to -0PERABLE status. QB-A.2.1 Initiate action to-Immediately establish an alternate method of decay heat removal. AtlQ A.2.2 Restore RHR-shutdown [72 hours] l cooling subsystem to OPERABLE status. l h (continued) l L i l l BWR/4 STS 3.9-10 05/24/90 1 l m

I;:Mie l V

c (k

RHR - High Water. Level t.-. R 3.9.7 LACTIONS (continued)' CONDITION. REQUIRED ACTION COMPLETIDN TIME B. ' Required Action and B.1 Initiate action to Immediately . associated Completion- . provide an alternate of Condition A not method of; decay heat-1

met, removal.

AND .e B.2 Suspend operations-Immediatelyf involving an increase in reactor decay' heat load. AND = B.3 Initiate action to I hour-restore Secondary -t ? Containment to OPERABLE status.

{

SEE s B.4 Initiate action to 11 hour restore one SGTS : subsystem to OPERABLE

status, o

AND s I hour i B.5 Initiate action to restore one Secondary Containment Isolation Valve and associated i instrumentation to OPERABLE status in each associated penetration not isolated. C t. t BWR/4 STS 3.9-11 05/24/90 h l Y

.v 4 RHR ~High Water Level l no 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify-that each required valve in the RHR-7 days shutdown cooling subsystem flow path is in its correct position or can be aligned to-its correct position. CROSS-REFERENCES -TITLE NUMBER-1 Secondary Containment Isolation Actuation Instrumentation 3.3.6.2 ECCS - Shutdown 3.5.2 Secondary Containment - Operating 3.6.4.1.1 Secondary Containment Isolation Valves - Operating 3.6.4.2.1 Standby Gas Treatment System 3.6.4.3 1 I 1 -BWR/4 STS 3.9-12 05/24/90

']v ' 78" 'RHR - Low Water' Level 3.9.8 -3.9i REFVELING DPERATIONS 3.9.8 Residual-Heat Removal (RHR) - Low Water Level 'LC0 3.9.8; ..Two Residual Heat Removal-(RHR) shutdown cooling subsystems shall be OPERABLE. APPLICABILITY: MODE 5 with water level < ( 23 )-feet above the. top of th'e. RPV flange. ACTIONS CONDITION REQUIRED ACTION -COMPLETION TIME =i A. One RHR shutdown-A.1 Initiate action to 15 minutes cooling subsystem restore RHR shutdown-1 inoperable. cooling subsystem to 1 OPERABLE status.

]

gg - j 'i A.2.1 Initiate action to-15 minutes establish a ( 23 ) feet of water above the top of reactor vessel flange, g- ]l A.2.2 Establ.ish alternate 7 days i decay heat removal l capabilities. bHD i A.2.3 Restore RHR-shutdown (7 days) cooling subsystem to OPERABLE status. 1 (continued) ) I ACTIONS (continued) BWR/4~STS 3.9-13 05/24/90 i ~ [ 1

Er. g.t a t' '..p. th. RHR.--Low Water Level = Jr*T- ~ 3.9.8 t" [, . CONDITION REQUIRED ACTION ' COMPLETION TIME 1 . B..Both RHR shutdown-B.1 Initiate action to Immediately i cooling subsyste's: restore one RHR m g inoperable. shutdown cooling subsystem to: OPERABLE status, f .QB nv B. 2. l' Initiate action to Immediately I establish alternate decay heat removal capabilities. 8HD B.2.2 Restore one RHR (72 hours] shutdown cooling subsystem.to OPERABLE status, f (continued) t 4 ? N } 4 a p l i. I a l i, "BWR/4 STS 3.9-14 05/24/90

o RHR Low Water Level 3.9.8 ACTIONS (continuid) CONDITION REQUIRED ACTION COMPLETION TIME _ C. Required A: tion and C.1 Initiate action to immediately associated Completion provide an alternate Time not met, method of decay heat removal. E C.2 Suspend operations involving an increase immediately in reactor decay heat

load, n

C.3 Initiate action to restore Secondary I hcur Containment to OPERABLE status. M C.4 Initiate action to restore one SGTS 1 hour subsystem to OPERABLE status. M i C.5 Initiate action to restore one Secondary I hour Containment Isolation Valve and associated instrumentation to OPERABLE status in each associated penetration not isolated. i BWR/4 STS 3.9-15 05/24/90

i',, O RHR Lo:s Water Level ? ~o. 3.9.8 SURVEILLANCE REQUIREMENTS SURVE!LLANCE FREQUENCY SR 3.9.8.1 Verify that each required valve in the RHR 7 days shutdown cooling subsystem flow path is in its correct position or can be aligned to its correct position. SR 3.9.8.2 Verify one RHR shutdown cooling subsystem in opeation and circulating reactor coolant. CROSS REFERENCES TITLE NUMBER Secondary Containment Isolation Actuation Instrumentation 3.3.6.2 ECCS - Shutdown 3.5.2 Secondary Containment - Operating 3.6.4.1.1 Secondary Containment Isolation Valves 3.6.4.2.1 Standby Gas Treatment System 3.6.4.3 4 i BWR/4 STS 3.9 16 05/24/90

Other Refueling LCOs i 0 3.9.9 3.9 REFUELING OPERATIONS 3.9.9 Other Refuelino LCOs B LCO 3.9.9 All related LCOs from other Technical Specifications Chapters shall be satisfied. APPLICABILITY: MODE 5 p i u CHAPTERS LCO'S 3.1 Reactivity Control Systems 3.1.1 Shutdown Margin I 3.2 Power Distribution Limits None 3.3 Instrumentation 3.3.1.1 Reactor Protection System Instrumentation Table 3.3.1.1; la, Ib, 2a, 2e, 8b, 11, 12, 13 3.3.1.3 Reactor Protection System Shorting Links 3.3.5.1 ECCS Actuation Instrumentation Table 3.3.5.1; la, Ic, Id, le, If, 2a, 2c 1, 3h, 41, Si 3.3.6.1 Primary Containment isolation Actuation Instrumentation Table 3.3.6.1; 6b 6c 3.3.7.1 Main Control Room Environmental Control System Actuation Instrumentation Table 3.3.7.1; 1, 5, 6, 7 3.3.8.1 Loss of Power Instrumentation 3.3.8.2 Reactor Protection System Electric Power Monitoring BWR/4 STS 3.9 17 05/24/90

I l' Other Refueling LCOs i: 9 3.9.9 i CHAPTERS LCO'S 3.4-ReactorCoolantSystem(RCS) 3.4.9 RCS Pressure and Temperature Limits 3.5 Emergency Core Cooling System 3.5.2 ECCS Shutdown (ECCS) i 3.6 Containment 3.6.1.3 Primary Containment Isolation Valves 3.7 Plant Systems 3.7.5 Main Control Room Environmental Control l System 3.7.6 Control Rc9m Emergency Air I Temperature Control (HVAC) System 3.8 Electrical 3.8.2 AC Sources - Shutdown r 3.8.5 DC Sources Shutdown 3.8.8 Distribution Systems - Shutdown (Needs additional review by Owner's Group) e BWR/4 STS 3.9 18 05/24/90 '}}

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