ML20236G907

Proposed Tech Spec Change 235,adding ASME Section IX Pump & Valve Program Definition & Changing Applicable Testing Frequencies to Ref Definition.Justification for Proposed Changes & Other Supporting Info Also Encl

ML20236G907
Person / Time
Site:	Browns Ferry
Issue date:	10/27/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18032A630	List: ML20236G907
References
TAC-R00250, TAC-R00251, TAC-R00252, TAC-R250, TAC-R251, TAC-R252, NUDOCS 8711030340
Download: ML20236G907 (76)

Text

{{#Wiki_filter:a 1 J q .q j j 1 I.j !l ENCLOSURE 1 -{ -l PROPOSED TECHNICAL'SPECIFICATI0NS' REVISIONS

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. BROWNS FERRY NUCLEAR PLANT- . UNITS 1, 2,;AND 3' (TVA'BFN 'TS 235) J .] l l i .. i l 4 ' 6 F i f i 'k ' + - 1.. .a b

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- 1. 0 : DEFINITIONS (Cont'd)' .I MM.: Surveillance requirements for ASME Section-XI Pamp and Valve'f., ' Program. Surveillance requirements:forJInservice. Testing of.ASME1 Code Class 1, 2,Jand23 components shall'be: applicable as fo110ws:7 j a 1.'LInservice. testing of:ASME Code? Class 1,12 -.and13 pumps'and' i valves shall-be performed:in-a'ecordance with-Section XI of.: ~ the ASME Boileriand: Pressure Code'and; applicable Addendafas-required by 10 CFR 50FSection:50.55a(g),..except where3 -specific written relief'has' been granted by the Commissions pursuant to 10-CFR 50. Section 50.55a(g)(6)(1)'.'. ~ ) .2. Surveill'ance' intervals:specified in<Section XIlofithe-ASMEl h Boiler and Pressure Vessel Code and: applicable Addenda.for the71nservice testing. activities required by;the.ASME Boiler?' i l .and Pressure Vessel Code'and applicable Addenda shall'be t 1 applicable as follows;in these technical specifications: ASME'Boller and: Pressure Vessel l : Required frequencies' ~ Code and applicable Addenda: 'for performing inservice ( O terminologyifor inservice; testing activities testing activities. At-leastionce per 7 days. Weeklyj 1 -Monthly .At'least once per 31 days' 4 Quarterly or'every 3 mo'nths' At least once,per 92. days 'q Semiannually or every 6 :nonths 'At least'once;per 184'daysL 1 Every 9 months ,At.-leastlonce.per"276; days' j Yearly-or annually At least'.oncesper 366 days j ~ j 4' 3. The provisions of Specification.1.0.11'are~ applicable to-the 1 above required frequencies for performing inservice testing; l activities. j d L 4. Performance of the above inservice 7.esting' activities shall j be in addition-to other;specified surveillance l requirements. J 5. Nothing in the 'ASME-Boiler and Pressure:Vesse1L Code shall be. construed to supersede the requirementsLoffany technical-specification.. l 1' 1 2 'l 'a ql .e a 1 ; o BFN 1.0-12 Unit 1 ,q 4 p V 1_ o

~1 c. Table 1.1' SURVEILLANCE FREQUENCY NOTATION-NOTATION ' FREQUENCY S

( Sh'i f t )

At least.once per.12-hours. D (Daily)- At least once'. per normalIcalendar. 24 hour day (midnight to midnight).. W-(Weekly) At least'once'per 7 days. .M (Monthly) At least once'per 31. days. Q (Quarterly) At least once per 3 months or 92 days. SA (Semi-Annually) At least once per 6 months or.184' days. l Y (Yearly) .At:least_once per year or 366' days."*' ~ R (Refueling) At-least once per/ operating cycle.. S/U (Start-Up) Prior to each reactor startup. N.A. Not applicable. P (Prior) Completed prior to each release. BFN' 1.0-13 Unit 1 'd i

n -3.3/4.3 REACTIVITY CONTROL -LIMITING CONDITIONS FOR OPERATION-SURVEILLANCE' REQUIREMENTS- . 3.3.E. If Specifications.3.3.C and.D 4 '. 3. E. Surveillance requirements;are above cannot be met, an orderly' as specifiedzin.4.3.C.and ..D shutdown shall be initiated and. above. the reactor shall be inLthe shutdown condition within '24 hours. F. Scram Discharr,e Volume (SDV) F. Scram Discharre Volume'(SDV)' ~ 1. The scram discharge volume 1.a. The scram discharge' drain and vent. valves shall -volume' drain and' vent be OPERABLE any time that Lvalves shall'be verified the reactor protection open prior to each-system is required to be startup and monthly. OPERABLE except as thereafter. The' valves specified in 3.3.F.2. may be' closed' intermittently for- "~"~ testing not.to exceed-l' hour =in.any 24-hour period-during operation. 1.b. The scram discharge. volume drain and vent valves shall be; demonstrated-0PERABLE in accordance with Specification 1.0.MM. 2. In the event any SDV drain -2. When it is determined' or vent valve becomes that any'SDV drain'or, INOPERABLE, reactor vent valve ~is. INOPERABLE, operation may continue the redundant-drain or provided the redundant vent valve shallLbe-drain or vent valve is demonstrated OPERABLE OPERABLE. immediately and weekly thereafter. 3. If redundant drain or vent. 3. 'No additional valves become INOPERABLE, " surveillance required, the reactor shall be in Hot Standby within 24 hours. BFN 3.3/4.3-11 Unit 1 W C-___

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l 1' . 3 '. 4 / 4 '. 4 STANDBY LIQUID CONTROL SYSTEM L . LIMITING. CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS g i l 3'. 4 - STANDBY LIOUID CONTROL SYSTEM-f4. 4 ' STANDBY-LIQUID CONTROL SYSTEM'- ] ~1 1 ' Applicability Applicability -l LApplies'to the. surveillance JI Applies to the operating status I: ' requirements.of the Standby #- l of the Standby Liquid Control' System. Liquid Control. System. .0bjective' Objective. .j To assure the availability of a To verifylthe'0PERABILITY;of;thez ] system with the' capability to' Standby Liquid Control! System." .i -shut down the' reactor and maintain. .l 'l the shutdown condition without the use of control. rods. Specification Specification A. Normal System' Availability 'A. Normal' System Availability-1. The Standby Liquid Control The operability of'the Standby. System shall be OPERABLE' . Liquid Control. System!shall'be. ) at all' times when there verified by the performance-is fuel in the reactor .of'the following tests: vessel and'the reactor is not in a shutdown condition 1. . Verify purap OPERABILITY - with all OPERABLE control in accordance with rods fully inserted except Specification 1.0.MM. as specified in 3.4.B.1. l

2. -At least'once during'each operating-cycle:

a.. Check that the setting-j of.'the' system relief valves'is 1,425 f, 7 5 - j 'psig'. ~ b. Manually initiate the system,' except explosive valves. pump-- , boron solution through- 'the recirculation path j and.back to the: l Standby' Liquid ~ Control _ Solution Tank. Minimum pump flow rate of 39 spm. against'a system head .J of 1,275'psig shall;be: BFN 3.4/4.4-1 Unit 1 n

.. ~. 3.5/4.5' COREANDCONTAINMENT-C00LkNGSYSTEMS' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE'E-REQUIREMENTS :

3. 5-CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability

-Applicability Applies to the operational App'liesIto the. surveillance status of the core and. . requirements of the core and' containment cooling systems. ' containment' cooling systems when .thel corresponding limiting condi - tion'for operation is in'effect. Objective Objective To assure the operability of 'To verify the OPERABILITY of the the core and. containment cooling-core and containment cooling systems under_all conditions for systems under all conditions for which this cooling capability is which this cooling capability.is-an essential response to plant aniessential' response to plant; abnormalities. abnormalities. Specification Specification. A. Core Spray System (CSS) A. Core Spray System (CSS)' l. The CSS shall be OPERABLE: 1. Core Spray System' Testing (1) prior to reactor Item Frequency startup from a Cold Condition, or a. Simulated Once/ Automatic Operating (2) when there is irradiated Actuation Cycle fuel in the vessel test and when the rer. tor vessel pressurr. b. Pump Opera-Per Specifi-is greater th'.n 'bility cation 1.0.MM atmospheric pressure, except as specified c. Motor Per Specifi-I in Specification Operated' . cation l1.0.MM 3.5.A.2. Valve Operability 'd. System flow. months Once/3' rate: Each y ' loop shall deliver at least 6250 gpm against a system head corres-ponding to a BFN 3.5/4.5-1 Unit 1 C _m__ m-- __-_-_.-___-_.___--__m. m _.-_m______.-__.m __a -ua_*_..__,._m

t 4 4 - 9 4 3.5/4.5 - CORE - AND CONTAINMENT COOLING SYSTEMS - 1 LIMITING CONDITIONS FOR OPERATION

SURVEILLANCE ' REQUIREMENTS 3.5.A Core Spray System (CSS) 4.5.A Core Spray-System (CSS)

-{ 4.5.A.1.d-(Cont'd) 105 psi' , differential. j'; pressure between.the reactor vessel-and the' primary containment. O e. Check' Valve -Per j Specification-1 0.MM. j l 2. If one CSS loop.is INOPERABLE, 2. When'it is determined that'one-the reactor may remain in core spray loop is INOPERABLE, operation for a period not to at-a' time when. operability is exceed 7 days providing required. the other-core spray all active components in. loop. the RHRS (LPCI mode), and-i the other CSS loop and the the diesel generators'shall be j RHR system (LPCI mode) demonstrated to be OPERABLE' l and1the diesel generators immediately. The OPERABLE core' { are OPERABLE. spray loop shall-be demonstrated o to be OPERABLE" daily thereafter. .I 3. If Specification 3.5.A.1 or Specification 3.5.A.2 cannot be met, the reactor shall be shutdown in the Cold condition within 24 hours, j 4. When the reactor vessel pressure is atmospheric and irradiated fuel is in the .j ,eactor vessel, at least one' core spray loop with one OPERABLE pump and associated j diesel generator shall be OPERABLE, except with the reactor vessel head removed as specified in 3.5.A.5 or prior to reactor startup as specified in 3.5.A.1. J l .i i BFN 3.5/4.5-2 Unit 1 l

) 13.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS-SURVEILLANCE REQUIREMENTS' LIMITING CONDITIONS.FOR OPERATION ~ 13.5.B Residual-Heat' Removal System' 4.5.B'. ' Residua). Heat ' Removal-System: -(RHRS) (LPCI and Containment' (RHRS),(LPCI.and Containment ') . Cooling). Cooling):, 1. 'The'RHRS shall be OPERABLE: 1 : a.:

Simulated ~' lOnce/~

Automatic. (Operating. (1) prior to a reactor. . Actuation. . Cycle startup from.a Cold. Test Condition..or (2) when there is b. Puico Opera -Per Specif1. irradiated fuel in bility ' cation 1.0.MM; the reactor vessel and when the reactor. vessel pressure.is c. Motor. Opera-Per'Specifi-greater than ted valve cation:1.0.MM operability atmospheric, r, 1 specified in j Specification-N '"# Pump Flow, Once/3 months j ~ through 3.5.B ~ Rate 1 m~ t. 20u. n .z d' Per'Specifi-i Test Check Valve ' cation 1.0.MM' '{ Each LPCI pump shall deliver L 9000 gpm against.an indicated' ) system pressure'of.125 psig. I Two'LPCI pumps in the:same' ' iloop shallzdeliver.12000 gpm-against-an; indicated.sys' tem j; pressure of 250.psig.. l ~ 2. With the reactor vessel 2. An air test on'the drywell-pressure less than 105 psig, 'and torus headers and: nozzles the RHRS may be removed shall.be. conducted once/5. q from service (except that two years. :- A -water test may be-RHR pumps-containment cooling performed on the torus header mode and associated heat -in lieu of the. air-test. H exchangers must remain OPERABLE) for a period not to exceed 24 hours while being drained of suppression chamber quality water and filled with primary coolant quality. water, provided that during cooldown two loops with one ~ J . pump.per loop or one' loop with two pumps, and associated diesel E generators in the core spray system are OPERABLE. BFN 3.5/4.5-4 -Unit 1 i_______________.__._____________._._._ ___._.____z__]

V --L. 3,m '3.5/4.5' CORE-AND CONTAINMENT COOLING' SYSTEMS' q' LI'MITING CONDITIONS FORTOPERATIONl SURVEILLANCE REQUIREMENTS

3.5.B. Residual Heat Removal' System' 4;5.Bc; Residual Meat' Removal' System.

-(RHRS) (LPCI'and Containment (RHRS)'(LPCI'and. Containment' Cool _ing)l . Cooling)- 8.'If-Specifications'3.5.B.1

8. :No additional surveillance.-

through 3.5.B.7.are not' met, _ required. an orderly shutdown shall be initiated and the reactor-shall~be shutdownLand" -placed in the' Cold Condition-

within.24 hours.

9. When the reactor vessel-9~. :When'the reactor.: vessel pressure;is atmospheric and pressure;is. atmospheric irradiated fuel is.in the the RHR. pumps'and: valves. reactor vessel,.-_at least one RHR.? ,that are required to:be- ~ loop with two pumps or two lo. ops _' OPERABLE.shall; bet u with one pump per loop shall'- demonstrated to,be:0PERABLE [' be OPERABLE. The pumps'- per-Specification 1.0.MM. associated diesel generators l must also be OPERABLE.

10. If the conditions of' 10.

No'additiontl. surveillance. Specification 3.5.A.5 are met, required. LPCI and containment cooling are not' required.

11. When there is irradiated fuel

11. :The RHR pumps'on the in the reactor and the reactor-adjacent units.which ' supply vessel pressure is greater than cross-connect capability, atmospheric, 2 RHR pumps and'

-shall be demonstrated to:bes associated heat exchangers and 0PERABLE~. monthly when;thei valves on an adjacent unit must cross-connect' capability' be OPERABLE and capable of i's required.1 supplying cross-connect ~ capability except'as specified in Specification'3.5.B.12 below. (Note: Because cross-connect capability is not a short-term requirement, a component is not considered INOPERABLE if. l: cross-connect capability can be restored to service within 5 hours.) s i t

l BFN 3.5/4.5-7 q

i Unit 1 -[ _-._m_.._m.. m..m. =.__ _m.U___ ___.__._.m-

i 'j -3.5/4.5 CORE AND ' CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 5.C -

RHR Service Water and Emergency! !4.5.CRHRServiceWaterand: Emergency-Equipment Cooling Water Systems Equipment Cooling Water Systems (EECWS) (EECWS)' 1, . Prior to reactor startup from - '1. a. Each of the RHRSW' pumps -a' Cold Condition,'9 RHRSW .b

normallyLassigned to?

pumps must be OPERABLE, with automatic service:on 7l pumps (including. pump D1 the EECW headers will( or D2) assigned to RHRSW be' tested ". 3 service and 2 automatically automatically each time starting pumps assigned.to the-dieseligenerators' EECW service, are tested. Each ofc thefRHRSW pumps and-all-associated es s en ti al.- con trol. valves for the EECW headers and-RHR-heat-exchanger headers shall'be' demonstrated to be OPERABLE in accordance with'. Specification.l.0.MM. b. Annually each RHRSW pumpfshall be flow-rate tested. 1To-be considered OPERABLE, each. pump. shall pump at 1 east 4500 gpm through its. normally' assigned flow 1 path. l l 1 BFN-3.5/4.5-9 Unit 1

t q_ y o_ ; e 4 i 4 ~ i h -3.5/4'.54 CORE AND CONTAINMENT CO'0 LING-SYSTEMS l-I E i 4 s o- <i o LIMITING CONDITIONS FOR OPERATIONc . SURVEILLANCE REQUIREMENTS M. .gg h-q .... s. 3.5<D Equipment. Area Coolers '4;5.D Equipment' Area Coolers-61~. The'eguipment area cooler 1 3Each equipment.arealcoolerT associated with each2RHRi isLoperated'1n conjunction, 4 ~ s ~

pump and the equipmentL with:the equipment; served 2

l area' cooler associated"

by,that particular. cooler;L

/ 4 with each: set.'of core-1 'therefore,itheiequipmentL ~ . area coolers:are tested._at ,j . spray pumps (A and C f [4 or B and-D) mustibe the same frequency.'as the . OPERABLE at all times. l pumps _which' they.. serve. ; .o Lwhen the pump or pumps. Y 1 servedLb'.that'. specific y ni sg cooler is. considered to. be OPERABLE. ' ' l t 2. When an.egulpment area cooler is not OPERABLE, the' pump (s)' served;by that? 1 cooler must1be considered INOPERABLE for technical ' specification' purposes.- q E. High Pressure Coolant Injection-E. High Pressure Coolanti System (HPCIS) Injection System (HPCIS). -i

1..The HPCI system shall be 1~. HPCI' Subsystem testing OPERABLE:

shalllbe performedtas 'follows:. ) (1) prior-to startup from a, .a. . Simulated,

0nce/i.

l' Cold-Condition, or . Automatic'. operating 'l i Actuation: Icycle_ -Testy Z (2) whenever there is b.- Pump.- LPeri irradiated. fuel in the' Opera-Specification. l reactor vessel and the -bility;, l' 0.MMi j i reactor vessel-pressure is greater than 172 psig, 'c. Motor Oper-. Per. except'as specified in ated Valve; _ Specification - -Specification 3.5.E.2.- Operability 1.0.MM: q d.. Flow Rate at-Once/3/ normal- ' months: reactor-vessel . operating: o pressure, i BFN 3.5/4.5-13:- Unit 1- .j 1 r l ..? I C ___.1 ______n___ ______m

y CORE AND C0N'AINMENT COOLING SYSTEMS. T 3.5/4.5 . LIMITING. CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-3.5.E High Pressure Coolant' Injection: ,4.5.E High' Pressure Coolant Injection ~ System (HPCIS)- System-(HPCIS), '4.5.E.1 (Cont'd) e, -Flow' Rate at 'Once/. j 1 '150 psig; Loperating cycle! ] I The HPCI pump shall:, deliver l at least 5000'gpm during { each. flow rate test. ~ j 2. If the HPCI system is. '2'. When.it'is determined that 4 INOPERABLE, the-reactor may' the HPCIS is. INOPERABLE,fthe' 'l remain in operation _for a ADS actuation' logic, the; .I period not to exceed 7 days, RCICS, the'RHRS (LPCI), and. l provided the ADS, CSS, RHRS-the CSS:shall' be (LPCI), and RCICS are ' demonstrated to be OPERABLE' OPERABLE.. immediately. The'RCICS and-ADS logic shall be demonstrated- !to be OPERABLE' daily thereafter. 3. If Specifications 3.5.E.1 or 3.5.E.2 are not met, an orderly shutdown shall be initiated and the reactor vessel pressure' shall be reduced to 122 psig'or less within 24 hours. F. Reactor Core Isolation Cooling F. Reactor Core Isolation Cooling System (RCICS) . System (RCICS) 1. The RCICS shall be OPERABLE:

1. RCIC: Subsystem testing shall be' performed as follows:

(1) prior to STARTUP from a Cold Condition, or-

a. Simulated Auto-Once/

matic' Actuation operating-(2) whenever there is Test cycle. irradiated fuel in the Per Specifi-reactor vessel and the

b. Pump

. cation'1.0.MM reactor vessel pressure ' Operability' is above 122 psig, except as specified in

c. Moto_r-Operated Per 3.5.F.2.

Valve ' . Specification ' Operability 1.0.MM' l BFN 3.5/4.5-14 Unit 1 l u.

$5 Cora and Containment Coolinr. Systema Surveillance Frequencies The testing interval for the core and' containment cooling systems is based on industry practice, quantitative reliability analysis, judgment, and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the availability of the core and containment I cooling system, the components which make up the system, i.e., R instrumentation, pumps, valves, etc., are tested frequently. The pumps and motor operated injection valves are also tested in accordance with Specification 1.0.MM to assure their operability. A simulated automatic l actuation test once each cycle combined with testing of pumps and injection valves in accordance with Specification 1.0.MM is deemed to be l adequate testing of these systems. When components and subsystems are.out-of-service, overall core and containment cooling reliability is maintained by demonstrating the operability of the remaining equipment. The degree of operability to be i demonstrated depends on the nature of the reason for the out-of-service equipment. For routine out-of-service periods caused by preventive maintenance, etc., the pump and valve operability checks will be performed to demonstrate operability of the remaining components. However, if a failure, design deficiency, cause the outage, then the demonstration of operability should be thorough enough to assure that a generic problem does not exist. For example, if an out-of-service period was caused by failure of a pump to deliver rated capacity due to a design-deficiency, the other pumps of this type might be subjected to a flow rate test in addition to the operability checks. j Whenever a CSCS system or loop is made inoperable because of a required l test or calibration, the other CSCS systems or loops that are required to j be operable shall be considered operable if they are within the required surveillance testing frequency and there is no reason to suspect they are inoperable. If the function, system, or loop under test, or calibration is found inoperable or exceeds the trip level setting, the LCO and the required surveillance testing for the system or loop shall apply. Redundant operable components are subjected to increased testing during equipment out-of-service times. This adds further conservatism and increases assurance that adequate cooling is available should the need arise. Maximum Average Planar LHGR. LHGR. and MCPR The MAPLHGR, LHGR, and MCPR shall be checked daily to determine if fuel burnup or control rod movement has caused changes in power distribution. Since changes due to burnup are slow, and only a few control rods are moved daily, a daily check of power distribution is adequate. BFN 3.5/4.5-35 Unit 1

m j $ i' ,1 3, o: v '~ 7 1 7 i 'd6 3'.6/416 ' PRIMARY' SYSTEM B'0UNDARYi 3 y, p ! LIMITING CONDITIONS'FOR-0PERATION SURVEILLANCE REQUIREMENTS? 1 ,1 (;

3'.6.C ; Coolant Leakage 4'.'6iC icoolant Leakage 9.1,

1 7 u-q. 2. Bothithe sump.'andlairtsampling- .2. Withith'emairisampling1 'l 1 d ~ system INOPERABLE,jgrab s .'systemsf shallt.be 0PERABLE(during-' . samples?shall be'obtained ,o reactor power operation'. From' cand.'after the date that one ofi ,andianalyzed at11 east Lonce! ~ )the'se-syst' ems';is made'or found-Eevery 24 hours. '4

• '/4

' + t.o beiIN0PERABLE for any: reason, j reactor power operation.-is. y

permissible;only'during

the:

succeeding 72-hours'. a i iJ -The-air > sampling. system mayi be removed?from service <for a r period of.4 hours for calibration, function testing. and' maintenance without1 .providing-a temporary t. monitor. 3. If the1 condition in 1 or 2 ab~ve cannot be' met,.anl orderly o l shutdown:shall be initiated 4 -r I and the reactor shallibe I shutdown in the Cold Condition l 7 ~ within'24 hours. 3.6.D.' Relief Valves 14.6.D. Relief Valves? e 1. When more than one relief valves .1. ? Approximately one-half of; are known to be failed, an. -all? relief.valvesishall / orderly shutdown shall be be bench-checked ~or' < initiated and the reactor replaced with a. M ~ depressurized to less than 105- ' bench-checked' valve = psig within 24 hours. .each:operatin's cycle. ~ A11L131 valves will;have-- beenf cheebd ^ or i replaced. upon:the completion.of.L every second cycle. t l-l- '2. In'accordance withL ' Specification;120.MNF., - eachLrelief 'valveLshalli be manually;" opened.unti10 'A 1 thermocouple andi acoustic monitors: downstream of the valve-i ' indicate. st'eam :is i ' flowing from'theTralve. BFN 3.6/4.6-10

Unit 1 y

e + L,~; S. s - g.

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hI' fia b 1,2 5 7. 73;6.C/4.6.C (Cont?d) t, n. reasonablyLin1 a matter'of a. f ew: hours.1 utilizing lthe. ava'ilable ' leakage;... 1 ~ "detectionc schemes,: and if the origin cannot be! determined -in Ja reasonably) -j short time,1the unit <should beishut'down to' allow furtherrinvestigationz; j ~ and corrective action. ] N The two spm limit for. coolant 1eakage' rate increase overTany"24; hour ~ t p' period is a limitispecified by NRC (Reference 2). JThistlimit;appliesi j c 1-Lonly'during the'RUN mode'to-avoid;being penalized!for_the expected! q coolant 1eakage increase. during pressurization. ~ d L j z The total leakage rate consist's ot a11' leakage,; identified and? c i . unidentified,:which flows._to the drywellefloor. drain and equipment drain,

q

sumps, Thecapacityofthedrywellffloorsumppumpis50:gpmland[theJcapacityoff h'

the drywell equipment sump pump'is?also 50igpm. LRemoval;ofl25'spm'.from= R either of these sumps can'be accomplished withLconsiderable margin;4 REFERENCE p 1. Nuclear System Leakage Rate Limits'(BFNp FSAR Subsection 4.10); 2. Safety Evaluation Report (SER) on IE.Bu11etin 82 1 (~ 3.6.D/4.6.D Relief Valves To meet the safety basis, 13 relief valves have beenfinstalled'onltNe' unit with a total capacity of 84.1 percent'of: nuclear boiler rated steam. .d flow at a reference pressure of (1,105L+ 1 percent);psig. The analysis g of the worst overpressure transient :(3-second closure:ofrall' main steam' line isolation valves) neglecting :theLdirect scram tvalve position scram)? results in a maximum vessel pressure which,"if a neutron 1fluz scram'iss assumed'considering 12 valves operable,.results in adequate' margin?to the ~ code allowable. overpressure limit'of.1,375Jpsig. To meet operational design, the analysis of..thel plant < isolation trans'ient. (generator load reject with bypass l valve. failure to.open)Lshows thati 12 of the 13 relief valves limit' peak systemrpressure to-arvalue whichLis. well below the allowed vessel overpressure'of;1,375lpsig. a Experience in relief valve operation shows that a' testing'of?50' percent} of the valves per year is adequate'to dete'et failures orideteriorations The relief valves are'benchtested'every second operating cycleLto ensure: that their setpoints are within the +11 percent tolerance. -Theirelief valves are testedJin place in accordance with Specification l'.0.HN.to-establish that'they will open and-pass steam. J ^{._ l .1 ) BFN 3.6/4.6-30 Unit 1 l L.i li I' E__.__.____________ 1

P ~r m-3 f f,[ 4 3.7/4.7 CONTAINMENT SYSTEM.3 yf .g LIMITING CONDITIONS JOR OPERATTON SURVEILLANCE REQUIREMENTS 3.7.A PRIMARY CONTAINMENT 4.7.A PRIMARY CONTAINMENT l 3. Pressure Suppression Cnamber -

3. Pressure Suppression Chamber-Reactor Building'Vg,uum Breakers Reactor Building Vacuum Breakers:

l

a. Except as opecified.in

a. The pressure suppression

.j 3.7.A.3.b below, two pressure chamber-re' actor building l suppression chamber-reactor vacuum breakers shall be q building vacuum breakers shall exercised in accordance with ,( be OPERABLE at all times when Specification 1.0.MM. and the- 'l 1 primary conta!,nment integrity associated instrumentativa is required. The setpoint including setpoint sVd1 be.' of the differential pressure functionally testod for lj instrumentation which actuates proper operatfor each thred ] l the pressure suppression months. ,a chamber-reactor building j vacuum breakers shall be 0.5 psid. ( n

b. From and c?ter the date

b. A visual examination andY P. hat one of the pressure determination that the l

l suppression chamber-reactor ' force required to open each I building vacuum breakers is vacuum breaker (eheck valve) l made or found to be INOPERABLE does not exceed 0.5 paid, 1 l will be mee each refueling 6 ) for any reason, reactor operation is permissible only outage. j during the succeeding seven l days, provided that the repair procedure does not violate primary containment integrity. 1 a 4. Drywell-Pressure Suppression

4. Drvwell-Pressure Suppression Chamber Vacuum Breakers

{_h_ amber Vacuum Breakers

a. When primary containment is

a. Each d;iwell-suppression required, all drywell-chamber vacuum breaker suppression chamber vacuum shall be testod in accordance 1

breakers shall be OPERABLE with Specification 1.0.MMi and positioned in the fully closed position (except during testing) except as j specified in 3.7.A.4.b and 3.7.A.4.c., below.

b. One tirywell-suppression

b. When it is determined that chamber vacuum breaker my two vacuum breakers are be nonfully closed so Iny, INOPERABLE for opening at a l

l .j BFN 3.7/4.7-10 q Unit 1 s 1 1 i i _J

D '( , @s # 4 . 3.7/4.7 CONTAINMENT SYSTEMS.- LIMITING CONDITIONS.:FOR OPERATION-- SURVEILLANCE REQUIREMENTS y ___. ....t'o Q i y /%'! -3.7.A- . Primary Containment 4.7.~A Primary' Containment

• j Q V,. N,

'3. 7. A. 4. b '. (Cont ' d') I4 ; 7. A. '4. b 2(Cont'd)s V 5~ R %. . time >when: operability;is ? as it;is determined to be-not? more than 3open as11ndicated'. . required,callcother.vacuam;. ~ Lbreaker valvesLshall.bej g y,,; by the position IJghts.- exercised?immediately-and-everyc 4 '15~ days thereafter until.thei LINOPERABLE' valve has:been returned to. norma 11serviceA .y h I

c. Two drywell-suppression ~

c.,Ehchavacuum;breakerivalv'e[1- ~ <shall be: inspected.forf. citamber vacuum breakers Proper operation of the 9 may:be determined to be. INOPERABLE for opening. (valve-and limit zwltches in'accordance withj ' Specification 1.0.MM.'

d. If Specifications 3.7 A.4.a..

d'.LA l'eak testLof the drywe11 '? J 3.7.A.4.b, or 3.7.A.4.c. to-suppression' chamber cannot be met, the . structure shall be conducted. unit shall be placed in a' .during each' operating' cycle.; Cold Shutdown condition.in.- - Acceptable leak rate.is an orderly manner within 0.14 lb/see of. prim'ary 24 hours, containment atmosphere with' 1 psi differential. f.( I s - f~/ 5. Oxyr.en concentration

5. Oxygen Concentration--

V'(( . h a. After completion of the fire-

a. The primary containment m..

related startup retesting program, ' oxygen concentrationishall= containment atmosphere.shall be .be' measured:and recorded.: E reduced to less than 4% oxygen ' daily. -The oxygen; with nitrogen gas during reactor measurement shall:be' adjusted ' llF power operation with reactor -toiaccount'for;the' uncertainty coolant pressure above 100 psig, L of the methodiused by: adding" except as specified in 3.7.A.S.b. a' predetermined error lfunctiona N .b. Within the 24-hour period- ,-b.LThe methods used to measure

.)

subsequent to placing the. reactor thel primary containment (. in the RUN mode following-a shut-oxygen. concentration.shall' down, the containment atmosphere be calibrated once every; oxygen concentration shall be refuelingicycle.- ~ -reduced to less than'4% by volume and maintained in this condition. l ;is Deinerting may commence 24 hours prior _to a shutdown.- l BFN 3.7/4.7-11 Unit 1 y 4 s [ 'l I ..a E- -im__ '____.i'._-___________._,_____, _ _ _ _ _ _,

._g. _----__-----.---x-- z Iff g. lyy y t. .~t, h t j e. 30y '

• b-

<F i 3.7/4.7 CONTAINMENT SYSTEMS' I.[N' LIMITING, CONDITIONS FOR OPERATION SURVrl(LANCE REQUIREMENTS - k.' ./; 4,h 3.7.A. Primary-containment 4. 7 EA.. Pe s, q qary Containment- / sp'<< .T Ni 'l V, }1 3.7.A.S.c (Cont'd) _4 .J

c. If Specification 3.7.A.S.a Q,

(4 g and 3.7.A.S.b cannot:be, met,) 's J l f an orderly shutdown shall.be g,. 'o,, -l 1, initiated and the reactor - g ..U 5 shall be in a Cold Shutdo ./ - C condition within'24 hours. p ,Av i. j t r. n 6. Drywell-Suppression /Chamb_e_r . (s r( 6. prywell-Suppression Chamber' ' Differential Pressure-Differential Pressure. q 1 .a

a. Differential. pressure.betweeb "a. The pressure differential:

p y l-the drywell and suppression 14tr.ynn; iihe dgwell and l , chamber shall be mCnteined-suppression chamber shall-at equal to or greater than~ .be recorded at leastto'nce eachishift. 1.1psit]exceptasspecified' d in (1) and (2) below: (1) This differential shall ) be established within ~ 7- ' l l*' 24 hours of achieving y *. g. E operating temperature .e j, and pressure. The, i, u l differential presshre. _. i n+ pry be reduced to less '/ l - tlan,1.1 psid 24 hours a# d. pr'o'r to a scheduled i ^ i s hrt.,down. J ( a w l 1 (2) This differential raay i, ~ ' boedecreased to less than 1.1'psid for a maximum.of four. hours y vN during requiredf y.. f>' operability t.esting of 3 the HPCI system, RCIC L 9 W, J system,andthedrywdl-pressure suppression / atamber vacuum breakers. f: \\ ;; t. h! y i 1 Y / ,s gpg 3.7/4.7-12sl 3 L y 6 unit 1 t +l j ) ,+ h C 13 's E__-_____:_______ _____.__a

~ 1 e -e. 3.7/4;7 CONTAINMENT SYSTEMS-LIMITING' CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENTS ' 3.7.B. Standby Gas Treatment System 4. 7 ~. B. ' Standby Gas Treatment. System 1 ] 3.7.6 (Cont'd) . b~. If the differential pressure of Specification 13.7.A.6.a cannot be maintained'and the differential pressure cannot be restored within the subsequent six-hour period.. an orderly' shutdown shall be 9 . initiated andi he reactor 4 t shall be in the Cold Shutdown-condition within 24-hours.

1. Except as specified in.

1. At least once per year,.

Specification 3.7.B.3 below, the=following conditions; all three1 trains of the shall-be demonstrated, o standby gas treatment system i shall be OPERABLE at all a. Pressure: drop across. S a-L times when secondary 7 - - - - - ~ --the combined HEPA containment integrity is filters.and charcoal-. required. adsorber banks is 'less. thant6 inches of water at a flow of 9000 cfm (1 10%). l b. The inlet heaters on q each circuit are tested in accordance

!j with ANSI N510-1975' I

and are capable of an outputiof at least 40 kW. c. Air distribution is uniform within 20%L across HEPA filters ~ and charcoal adsorbers, l l BFN 3.7/4.7-13l Unit 1 m_-m_m___-_m__.__m

h j o 1 L 3'7/4.7 = CONTAINMENT SYSTEMS:- LIMITING CONDITIONS FOR OPERATION-

SURVEILLANCE REQUIREMENTS 3.7.C. S_e_condary Containment

[

4. If refueling zone-secondary

o. containment cannot be-maintained, the following

j conditions.shall be' met

? -4 .a. Handling 1of. spent fuel and j all= operations over spent 4 fuel pools and open reactor wells containing-fuel shall l .be prohibited. l

1

b. The standby gas treatment 4

s a -system suction to the l refueling zone will be l blocked except for a contro11edaleakaBe area sized to assure the achieving of a. vacuum of at least 1/4-inch of' water 1 and not over 3 inches of .i water in all three reactor zones. D. Primary Containment Isolation Valves D.* Primary Containment Isolation. Valves 1 l

1. During reactor power operation,

1. The primary containment all isolation valves listed in isolation valves-i Table 3.7.A and all reactor surveillance-shall be i

l coolant system instrument line performed as'follows: flow check valves shall'be OPERABLE except as specified

a. At least'once per' in 3.7.D.2.

operating cycle, the-I OPERABLE isolationivalves. l thatiare' power operated'and ~ automatically initiated i sh'all:be tested for simulated l automatic- . initiation 1and in: accordance with' Specification.1.0.MM,. tested-for closure times'. 1 l. 3

f..

BFN 3.7/4.7-17 ' Unit 1

y l 3. 7 / 4 '. 7 CONTAINMENT SYSTEMS' n LIMITING CONDITIONS FOR OPERATION ' SURVEILLANCE REQUIREMENTS

3.7.D.. Primary Containment Isolation ~

5.7.D.:PrimaryContainmentIso5ation ! Valves-Valves

4. 7. D.'li ( Cont '. d )

~ b.LIn'~accordance with ~ Specification 1.0.MM; -all normally:open power l J operated isolation' valves.-

shall'be functionally tested.

c. AtLleast twice per week,.the-main steam line power-operated

' isolation valves-.shall be. exercised'one at a time'by_.- i partial closure and subsequent reopening. l

]

ld. At least.once'per operating"

cycle,.the operability of the reactor. coolant 1 system instrument linelflow' check valves'shall

be verified.

2. In the event any isolat! ion valve -

. Whenever an; isolation valve specified in Table 3.7lA becomes listed in Table'3.7.A-is INOPERABLE, reactor power. INOPERABLE,.the position'of at operation may continue provided least one other valve!in each line having an-INOPERABLE valve at least one valve in each line having an-INOPERABLE valve is..in shall.be recorded daily.. the mode corresponding-to:the isolated condition.

3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall 1

be in the Cold Shutdown condition sj within 24 hours. T .1 ') BFN 3.7/4.7-18 . Unit 1 1

)

'j .. ] 4

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.G. Containment Atmosphere 4.7.G. Containment Atmosphere Dilution System (CAD) Dilution System (CAD)_ 1. The Containment Atmosphere 1. System Operability Dilution (CAD) System shall be OPERABLE with: Cycle each-solenoid a. systems capable of operated air / nitrogen f a. Two independent valve through at j supplying nitrogen least one complete to the drywell and cycle of full travel-l torus. in accordance with Specification 1.0.MM,- and.at least once per l month verify that I I each manual valve in the flow path is open. b. A minimum supply of-b. Verify that the CAD 2,500 gallons of System contains a liguid nitrogen per minimum supply of i 2,500 gallons of system. liquid nitrogen twice per week. 2.* The Containment Atmosphere 2. When FCV 84-8B is Dilutic's (CAD) System shall INOPERABLE, each be OPERABLE whenever the solenoid operated rtactor mode switch is in air / nitrogen valve the "RUN" position. of System B shall be cycled through at least one complete cycle of full travel and each manual valve in the flow path of System B shall be verified open at-least once per week. 3. If one system is INOPERABLE, the reactor may remain in f operation for a period of 30 days provided all active components in the other system are OPERABLE. 3.7/4.7-22 BFN Unit I w_

3.7/4.7 BASES (Cont'd) and 5 - Process lines are designed to remain operable and mitigate Groups 4 the consequences of an accident which results in the isolation of other process lines. The signals which initiate isolation of Groups 4 and 5 process lines are therefore indicative of a condition which would render them inoperable. Group 6 - Lines are connected to the primary containment but not directly to the reactor vessel. These valves are isolated on reactor low water level (538"), high drywell pressure, or reactor building ventilation high radiation which would indicate a possible accident and necessitate primary containment isolation. Group 7 - Process lines are closed only on the respective turbine steam supply valve not fully closed. This assures that the valves are not open when HPCI or RCIC action is required. Group 8 - Line (traveling in-core. probe) is isolated on high drywell pressure or reactor low water level (538"). This is to assure that this line does not provide a leakage path when containment pressure or reactor water level indicates a possible accident condition. j l The maximum closure time for the automatic isolation valves of the primary l containment and reactor vessel isolation control system have been selected in l l l consideration of the design intent to prevent care uncovering following pipe ) breaks outside the primary containment and the teed to contain released j fission products following pipe breaks inside ths primary containment. l In satisfying this design intent, an additional margin has been included in specifying maximum closure times. This margin permits identification of degraded valve performance prior to exceeding the design closure times. In order to assure that the doses that may result from a steam line breat do not exceed the 10 CFR 100 guidelines, it is necessary that no fuel rod perforation resulting from the accident occur prior to closure of the main steam line isolation valves. Analyses indicate that fuel rod cladding l perforations would be avoided for main steam valve closure times, including instrument delay, as long as 10.5 seconds. j 1 These valves are highly reliable, have low service requirements, and most are normally closed. The initiating sensors and associated trip logic are also checked to demonstrate the capability for automatic isolation. The test 4 interval of once per operating c cle for automatic initiation results in a l failure probability of 1.1 x 10-that a line will not isolate. More j i frequent testing for valve operability in accordance with Specification 1.0.MM results in a greater assurance that the valve will be operable when needed. l l I The main steam line isolation valves are functionally tested per Specification 1.0.MM to establish a high degree of reliability. l { l The primary containment is penetrated by several small diameter instrument j lines connected to the reactor coolant system. Each instrument line contains a 0.25-inch restricting orifice inside the primary containment and an excess j flow check valve outside the pririary containment. 3.7/4.7-50 I BFN Unit 1 1 1

"T~ E ,j J1. 0 - DEFINITIONS (Cont'd) MM.7 Surveillance Requirements'for ASME'Section XI' Pump and Valve ~ Program:. Surveillance requirements for Inservice:Testingsofl .ASME Code Class 1 2, and 3 componentsjshall;befapplicable as follows: ,1. Inservicetesting:ofASMELCode'ClassL1,r2,and?3pumpsand (valvesL.shallbeperformedjin;accordance;withfSectionXIjof /the.ASME Boiler-and Pressure: Vessel Code.and: applicable; Addenda asLrequired.by: 10LCFR;50..Sectioni.50.55a(s), exceptJ where' specific;writtenirelief;has,been' granted,by;theh!L

Commission' pursuant to 10 CFR 50,7 ection 50.55a(g)(6)(1)~.-

S l 2. Surveillance intervals'specified-in'.Section XI of the'A'SME, Boiler and Pressure.VesseliCode'and. applicable l Addenda'fori the. inservice testing 1 activities: required by the:ASME1Boller and Pressure Vessel' Code and applicableLAddenda.shall be' applicable as. follows -in these _technicalispecifications* - ASME Boiler.and Pressure:Vesseln l. -Required _ frequencies! code and applicable Addenda 'for performinglinservice a l terminology for' inservice ', testing ^ activities testing activities: Weekly 'At(least once per.,7: days:

Monthly,

..At leastionce'per;31" days.' Quarterly or.every 3 months _At leastLonceiper792 days Semiannually or every 6 months. At least?once per;184.daysi Every 9 months. LAt"leastlonce'per.276 days ' Yearly or annually-At leastio'nce;perf366fdays.

. a N

TheprovisionsofSpecification;1.0.LL5are:applicabletoithe? 3. above required frequencies,for performing inservice' testing- . activities. 4. Performance of the'above' inservice testin's actisitiesishallm be.in addition to other specified. surveillance requirements. ] ~ 1 5. Nothing in the ASME-Boiler and Pressure Vessel Code shill be... construed: to supersede the'. requirements of anyltechnical-specification. -l 1 l'i U J } v .d BFN 1.0-11 4 Unit 2. 1)a L ll.. a 0* i t _i 1 -.__E_____.___i_E_m_______,_j.

El SktL 3 .g i Table 1.1. .1 SURVEILLANCE' FREQUENCY'MOTATION: ..j f ' NOTATION FREQUENCYi c. a S (Shift) At least once per 12. hours. ') 'I D (Daily) At-least once per norma 1' calendar l 4 24 hour dayf(midnight'to midnight). i W (Weekly) ' At least-once per?71 days. D ? M (Monthly) .At:least once'perJ31:, days. Q (Quarterly) .At'least once per 3fm~o'nths or 92 days. I SA' (Semi-Annually) At'least;onca per:6 months'or 184, days; l Y (Yearly) .AtLleast once per year or 366 days'.- ' l, R '(Refueling) eat least:encefper' operating cycle. l S/U (Start-Up) Prior to each reactor startup. i N.A. Not applicable, i P (Prior) Completed prior to each release, q i t f a l i BFN 1.0-12 Unit 2 .j a. we w_i

3.3/4.3 -REACTIVITY CONTROL s LIMITING CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENTS-1 Surveillance requirements are E 4.3.E. 3.3.E. If Specifications 3.3.C and' D above cannot be met, an orderly. as specified.in 4.3.C and .D-shutdown,shall be initiated and. above. as the reactor shall be:in the shutdown' condition within' 24 hours. 1 F. Scram Discharge Volume (SDV) F. Scram Discharge Volume"(SDV)- 1. The scram discharge volume 1.a.-The scram discharge: drain.and' vent valves shall . volume' drain and~ vent valves shall'beiverified. be OPERABLE any time that the reactor. protection, 'open prior to each' STARTUP'and monthly-system is required to be tacreafter. The valves OPERABLE except as' specified in 3.3.F.2. may be closed' intermittently for-testing not to' exceed 1 hour in any 24-hour. -period during operation. i 1.b. The scram disch'arge volume drain and vent': ~ valves shall be demonstrated'0PERABLE -in accordance with. Specification 1.0.MM.. 2. In the event any SDV drain 2. When it is determined-or vent valve becomes that any SDV drain or INOPERABLE, reactor vent valve is' INOPERABLE, operation may continue the redundant drain.or-provided the redundant vent valve.shall be drain or vent valve is demonstrated OPERABLE-OPERABLE. immediately'and weekly thereafter. 3. If redundant drain or vent 3. .No additional < valves become INOPERABLE, surveillance required. the reactor shall be in Hot Standby within 24 hours. l j BFN 3.3/4.3-11 l Unit 2 I - i _._.l__.____

Il 3.4/4 41 STANDBY'Lf0VID CONTROL-SYSTEM LIMITING CONDITIONS FOR 0PERATION . SURVEILLANCE REQUIREMENTS ~ 3.4: STANDBY LIQUID CONTROL SYSTEM

4. 4-

' STANDBY LIOUID CONTROL SYSTEM : Applicability Applicability-1 i Applies to.the operating status. AppliesLto.the surveillance' requirements.offthe Standby ) of.the' Standby Liquid Control' l-Liquid' Control" System.- System. Objective ] l Objective Toverifythe.operabilityofIthe.

To essure the' availability.of.a y

syst em with' the capability. to. Standby Liquid Control System. l' shut down the reactor-and maintain 'the shutdown condition without the use of control rods. Specification Specification A. Normal System Availability A. Normal System Availability ~ 0 1. 'The Standby Liquid' Control -The operability of.the Standby' System shall be OPERABLE. Liquid; Control System <shall be at all times when there ' verified by_the performance-is fuel in the reactor .of the following tests: vessel and the reactor is not in a shutdown condition 1.

Verify pump OPERABILITY j

with all OPERABLE -control-in accordance with .l rods fully inserted except . Specification 1.0.MM. as specified in 3.4.B.1. 2. At least once during each operating. cycles a. Check that the setting. l of the' system relief valves is 1,425 1 75 psig.- b. M'anually initiate the system,.except i explosive;talves. Pump-boron solution'through the' recirculation path' and back to the. Standby: Liquid Control-Solution Tank. .i-Minimum pump flow: rate of 39 gpm against'a system head-of-1,275 psig.shall be BFN 3.4/4.4 Unit 2. L i M.____________________________ r_ _.._________________i

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING. .4 SYSTEMS SYSTEMS Applicability Applicability. Applies to the operational Applies to the surveillance status of the core and requirements of the core and containment cooling systems when containment cooling systems. the corresponding limiting condi-tion for operation is in effect. Objective Objective To assure the operability of To verify the operability of the j the core and containment cooling-core and containment cooling systems under all conditions for systems under all conditions for which this cooling capability is which this cooling capability is an essential response to plant an essential response to plant abnormalities, abnormalities. Specification Specification A. Core Spray System (CSS) A. Core Spray System (CSS) 1. The CSS shall be OPERABLE: 1. Core Spray System Testing. (1) prior to reactor Item . Frequency startup from a cold condition, or a. Simulated Once/ Automatic Operating 1 (2) when there is irradiated Actuation Cycle fuel in the vessel test and when the reactor vessel pressure b. Pump Opera-Per Specifi-is greater than bility cation 1.0.MM atmospheric pressure, except as specified c. Motor Per Specifi-in Specification Operated cation'l.0.KM 3.5.A.2. Valve i Operability d. System flow Once/3 rate: Each months loop shall deliver at least 6250 gpm against a syctem head corres-ponding to a 1 BFN 3.5/4.5-1 Unit 2 j 9

o +.

it

.i i d 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS a lhMITING CONDITIONS FOR OPERATION .. SURVEILLANCE REQUIREMENTS! a l 3.5.A' Core Spray System (CSS)-

4. 5. A ' : Core Spray System'(CSS).

t ~ ~ ' 4. 5. A'.,1. d ( Con t ' d ) d

105~ psi $

-Q? dif f erenti a1'- pressure .f between thei

reactor

vessel

.E

and the;primaryi 4

containment..- e.. Checit Valve' Per. ' Spe'ci fi c ati'on :. 1.0.MM. -2. If one CSS loop is. INOPERABLE, 2. When it^is: determined that ones i1 1 core - spray: loop - is l INOPERABLE,

y the reactor may remain-in

c

~ r I

operation for a period not to ~

at:a;timez.when operability l's- / j exceed 7-days providing'- required. the other: core spray:. y all active components in loop; the'RHRS (LPCI mode);.;and; <l the other CSS loop and the-tho' diesel-generatorsLshall bet. 1 RHR system (LPCI mode) .' demonstrated:'to be. 0PERABLE and the diesel generators immediately. :The~ OPERABLE core-are OPERABLE. spray;1oop shall.be demonstrated 'to;be' OPERABLE. daily thereafter. ~f 3. If Specification 3.5.A.1 or 'i Specification 3.5 A.2 cannotn be met, the reactor'shall be: shutdown in the ColdJ Condition within 24 hours. 1 4. When the reactor vessel pressure is atmospheric and 3 irradiated fuel:is'in the reactor vesse1~, at least one: i core spray loop'with one OPERABLE pump and associated . [' diesel generator'shall be-OPERABLE, except with the; j j. l l' reactor vessel head removed j as specified in 3.5.A.5 or ~ i prior to reactor startup'as specified in~3.5.A.1. i 3.5/4.5-2 EFN Unit 2 a. >hs' i__...._.:_ .__1_..__.___b-

Y l a 3.5/4.5 CORE AND' CONTAINMENT COOLING SYSTEMS ~' 1 . SURVEILLANCE REQUIREMENTS-LIMITING CONDITIONS FOR' OPERATION 3.5.B' Residual Heat Removal' System 4.5.B. Residual Heat Removal System ] (RHRS) (LPCI and Containment; a (RHRS) (LPCI and Containment-d Cooling). Cooling) i

1. a.

SimulatedL Once/- d 1. The.RHRS-shall?be OPERABLE: p Automatic ~ Operating i L . Actuation'. , Cycle- ' ' q (1) prior to a reactor. Test startup from a Cold Condition, or (2) when there is .b. Pump Opera.'Per-irradiated fuel in bility ~ Specification .l 1.0.MM. j the reactor vessel and when the reactor-q vessel pressure is' c. Motor Opera-Per . red valve Specification greater than atmospheric, except as operability.1.0.MM { specified in: f Specifications 3.5.B.2, .d. Pump Flow, Once/3 Rate' months. through 3.5.B.7. J -e. Testable Per l Check Valve Specification 1.0.MM Each LPCI pump shall deliver 9000 gpm'against an indicated system pressure of 125 psig. Two LPCI pumps in the same loop shall deliver 12,000 gpm against an indicated system-pressure of 250.psig.- 2. With the reactor vessel

2. An air test'on~.the drywell pressure less than 105 psig, and torus. headers and nozzles the RHR may be removed shall be conducted'once/5 I

from service (except that two years. A water test may be l RHR pumps-containment cooling performed on the torus header mode and associated heat. in lieu of the air.' test.. j exchangers must remain OPERABLE) for a period not to exceed 24 hours while being drained of suppression chamber quality water and filled with primary coolant quality water, provided that during cooldown'two loops with one pump per loop or one- ' loop with two pumps.and associated diesel generators, I in the core spray; system are OPERABLE. BFN 3.5/4.5-4. Unit 2 ~

7,,,----_---- 7 .l M' t .J: g' 4

]

^ Uh -3.5/4.5 CORE'AND CONTAINMENT: COOLING SYSTEMS: -LIMITING CONDITIONS'FOR 0PERATION1 l SURVEILLANCE REQUIREMENTS q,

3. 5.B -

Residua 3 Heat Removal' System- .4.5.B. Residual' Heat Removal SystOm -(RHRS)'(LPCI and Containment? (RHRSl?(LPCI and: Containment- ' Cooling). ,d ' Cooling) .o

8. If Specifications 3.5.B.1.

84 LNo additionalisurveillance-f through:3.5.B.7 are'not met, required.. 'an orderly. shutdown shall be s initiated and the. reactor-shall'be, shutdown and:. Lplaced'in the Cold. Condition within 24 hours.' l

9. ;When;the reactor'vesse1J 9.

When the reactor' vessel . pressure:is ' atmospheric andi pressure -is atmospheric,:. O l irradiated fuel is.in.the Lth'e RHE'pumpsfand-valves? '~ 9 reactor' vessel', at.least one RHR: that.are requiredito'bei loop with two pumps oretwo loops! ' OPERABLE.shallLbe with one pump pe'r loop shall demonstrated;to;be OPERABLE 1 be OPERABLE...The pumps per Specification 1.0 MM. associated diesel generators must'also be'0PERABLE.

10. If the conditions of 10.

No additional! surveillance I Specification 3.5.A.5 are met, required. l LPCI and containment: cooling are not' required. 1 1

11. When there is irradiated fuel

-11. The RHR' pumps =on the i in the reactor and the reactor adja' cent units: whichisupply - vessel pressure is greater than cross-connect) capability atmospheric, 2'RHR pumps and shall be.' demonstrated:to be a associated. heat exchangers and. OPERABLE-monthly when the; D valves on an adjacent unit must cross-connect capability a be OPERABLE and capable of~ is. required. supplying cross-connect capability except.as specified in Specification.3.5.B.12 below. l (Note: Because cross-connect capability is not a'short-term-j requirement, a' component is not considered INOPERABLE if-j ' cross-connect' capability can be-restored to service within 5 hours.)- i'! 't 3.5/4.5-7 BFN Unit 2 1 I i A _u.__.'_'l_E_..i._.m,A.

7

o i

j Qt W .f. 23f5/E.SiCdREAND'CONTAINMENTCOOLINGSYSTEMSl R

1. ^

i ' 4 ' LIMITING. CONDITIONS'FOR OPERATION. SURVEILLANCE REQUIREMENTS !4.5.C3 KRHR Service Water and 3.5.C RHR Service Water and Emergency. (. Eguipment Cooling-Water Systems' ' Emergency Equipment-l. -(EECWS) -Cooling Water Systems I n' .(EECWS); .C 2 l . Each6fftheRHRSWpumps. 3.' Prior.toLreactorLstartup from

1:.

,a. 7

norma 11yLassigneditoy

'a Cold Condition,c9 RHRSW..

pumps must.be OPERABLE; with automatic 1 service lon.;

,;j !a 7l pumps',(including onetor4 the'EECW headersiwill u, ') pumps D1,yD2,'B2 or?B1) ' be tested' automatically leachTtime' T; j assigned:to RHRSW' service v. j p and 2 automatically starting. the. diesel generatorsi 9 L . pumps: assigned to'EECW: 'are tested.1 Each . service. Eof'the,RHRSW"pumpst andi y ~ ll associated: J a .essentialicontro11# I valves'for the;EECWi ' headers 1 andlRHR. heat' l ,aH . exchanger headers > .sha11Ebefdemonstrated, ~to be OPERABLE ~in? Laccordance with:... Specification 1.0.MM. j .]

b. / Annually each RHRSW pump shall1be' flow-rate tested.' To a

be' considered. 0PERABLE,(each pump: -sha11' pump lat 1 east-4500.gpm through;its a Enorma11yfassignediflow: l , path, l b l s BFN 3.5/4.5-9. Unit 2 a . :p- - ___ii_______ -

g / s,'i t y f i i ~

3.5/4.5 CORE AND CONTAINMENT COOLING' SYSTEMS' SURVEILLANCEREQUIREMENTh

' LIMITING' CONDITIONS FOR OPERATION. 3.5.D. Equipment' Area' Coolers .4.5.D; Equipment'Afea Coolersi '1..Each equipment 1 area coolorf 1. 'The equipment' area cooler.: .is. operated.in conjunction associated with each RHR withL the.eguipment servedi Jpump and'the equipment; L area' cooler,associatedL by that particular, cooler;E with each set'of: core therefore,;the equipment f iarea coolerstare'testedfatt . spray l pumps (A:and?C .or B and:D):must be.' thelsame' frequency as;the ~ 1 OPERABLE:at all times: pumpsiwhich they. serve.

when-the. pump or pumps.

.; served by that specific cooler is considered to' q. be OPERABLE. '2. When an equipment area. cooler is not-OPERABLE, the, pump (s) served by that- ~ cooler must be considered INOPERABLE for technical specification purposes'. 'l' E. High Pressure Coolant Injection 'E. High Pressure Coolant-System ti'DCIS) Iniection. System'(HPCIS)! 1. The HPCI a,vstem shall be' .1. 'HPCI'Su$ system: testing, shall. be~ performed as.' OPERABLE: follows: (1) prior to startup'from a

a. _ Simulated'

.. Once/ ' Cold Condition, or- ' Automatic:

operating',

Actuation < Test -- cycle 1 (2)- whenever there is. b'. pump- _Per:... irradiated fuel in the Opera'- Specification reactor vessel and the, ,1 bility.. [1'. 0.MM, reactor ~ vessel pressure -per is greater than-122 psig, c'. -: Motor' Oper- : except as.specified in ated' Valve (-

Specification Specification 3.5.E.2.

Operability: 1.0.MM: '. Flow Rate at=.'Once/32 d ~ normal? months'- reactor. 'l vessel j operating 1 ' pressure a BFN 3.5/4.5-13 Unit 2 [ y 1

.0

y 7,__ j/ 3, L' ) y; 3 ~ J' , W; 3i5/4i5' CORE AND~ CONTAINMENT' COOLING SYSTEMS d -r -LIMITING CONDITIONS'FOR 0PERATION SURVEILLANCE-REQUIREMENTS' 11 s 3.5.E

High Pressure Coolant Injection'}' '4.5;Es High Pressure Coolant' System'(HPCIS)

' Injection > System-(HPCIS)? N 4.5.E.1. (Cont'd) ' i ( c 'e. ! F1ow'Ratefati.Once/.. 4: ~ 1 .150 psig-operatingi' .cyc e> i l s The HPCI pump shall deliver: 0 ' at. leastl 5000f gpm during'.- .N ,each: flow' rate test. '2. If the HPCIIsystem is. -2. When!it-is determined that INOPERABLE, the reactor may. the HPCISqisfIN0PERABLE,ithe' 3 . remain in operation forma- .ADSLactuation logic. the.. l period not to exceed 7 days,

RCICS, the;RHRSf(LPCI)',land provided the ADS, CSS, RHRS'

-the CSS.shall be' L (LPCI), and RCICS.are. demonstrated to be.0PERABLEL .1 -OPERABLE. Immediately; '.The;RCICS'andi - LADS logic shallibel demonstrated, .to be OPERABLE daily thereafter. 3. If Specifications'.3.5.E.1 s or.3.5.E.2 are not met, an orderly shutdown shall-be initiated and the reactor vessel pressure L shall be reduced to 122-l psig or le'ss within 24 hours. F. Reactor Core Isolation Coolin'g. F. Reactor Core Isolation Cooling-ll System-(RCICS) System (RCICS) J ~

l 1.

The'RCICS shall be OPERABLE: 1.~RCICl Subsystem testing'shall l l be performed as follows:- =j (1) prior to STARTUP from-a Cold Condition 6or..

a. Simulated' Auto-.-Once/;

' matic Actuatio'n." operating E I -(2) whenever there is. Testi cyclei R irradiated fuel-'in ther ] reactor vessel.and'the. .b. Pump Per Specifi. cation 1.0.MM ~ reactor vessel pressure Operability.: ir above 122Tpsig,- except as specified.in^

c. Motor-Operated -PerTSpecifi-3.5.F.2.

- Valve. ' cation l'0.MM Operability; -- B FN 3.5/4'.5-14 Unit 2 'M C

f c,. 4'. 5 Core and Containment Cooling Systems' Surveillance Frsquzncias ~ z' The testing interval for thefcore-and containment;coolingjsystems'ise based on industry. practice,. quantitative reliability analysis,,judgme'nt-and practicality. - The' core cooling systems have: not,been designed to! bey fully testable.during operation. For example,.in.tho' case of~the HPCI, automatic initiation during power-operation.would result;in pumping; cold' + water _into the reactor vessel which is -not desirable.: LComplete ADSL testing during' power operation causes'an; undesirable loss-of-coolant; inventory..To increase the availabilityLof the' core and containment; cooling system, the' components which make.up the system..i.e..: instrumentation, pumps,; valves, etc.,.are tested frequently. ;Theipumps and motor. operated injection valves are also tested.in*accordance with~ Specification 1.0.MM to assure their operability /.A' simulated automatic-actuation test once each cycle' combined with: testing of. pumps and; ~ ~ injection valves in accordance with Specification l.0.MM-is deemed to be, . l. adequate testing of these systems. When components and: subsystems.are out-of-service, overal1Ecore and' containment cooling reliability:is maintained.by demonstrating the ~ operability of the remaining' equipment. 'The degree.of operability.to be demonstrated depends:on the nature of.the reason.-for the out-of-service-equipment. -For' routine out-of-service : periods caused by preventive maintenance, etc., the pump and' valve operability (chet b will'be . performed to demonstrate operability;of,the remaining componentsb However, if a failure,. design deficiency, cause the outage. then'the-demonstration of operability should be thorough enoughito assure that'a generic problem does not exist. Fortezample,-iflan;out-.of-service period was caused by. failure of-a pump to deliver. rated capacity'due to a design: deficiency, the other pumps of this type might be subjected to 'a' flow-q' rate test in addition to the operability ~ checks. Whenever a CSCS system or' loop.is made inoperable because of a required test or calibration, the other CSCS systems or loops that are' required to-be operable shall be considered operablatif they.are within the required surveillance testing-frequency and'there is no reason tol suspect theylare inoperable. If the function, system, or. loop under testLor calibration-is found inoperable or exceedt-the trip-level setting, the LCO'and the required surveillance testing for the system or loop shall apply. ~ y Redundant operable components are subjecte'd to increased testing'during_ equipment out-of-service times. This adds further conservatism and. 1 increases assurance that adequate cooling is available should the need f arise. Maximum Average planar LHGR, LHGR.'and MCpR-The MAPLHGR, LHGR, and MCPR shall be checked' daily to determine if' fuel 1 burnup or control rod movement has caused changes in power. distribution. j 1 Since changes due to burnup are slow. and only a few control rods.are moved daily, a daily check of power distribution is adequate.'- l 1 BFN 3.5/4.5-33 Unit 2 i /. _ m

i 1 1 3.6/4.6 PRIMARY SYSTEM BOUNDARY LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l 3.6,C. Coolant Leakage- ~4.6.C. Coolant Leakage-2. Both'the sump and air: sampling 2. With the air samplingi ~ 1 ~ systems shall be OPERABLE during . system INOPERABLE.-grabL. reactor power operation. From ' samples shall be obtained ] and after the date-that one of and analyzed at least once every'24 hours, these systems is made-or found. jl to be INOPERABLE for any reason, reactor power operation is-permissible only during the succeeding 172 hours. The. air sampling system may be removed from service for a period of 4 hours for calibration, function testing, and maintenance without providing a temporary ~ j monitor. 3. If the condition in 1 or 2 above cannot be met, an orderly 1 shutdown shall be initiated and the reactor shall be shutdown in the Cold Condition within 24 hours. .j 3.6.D. Relief Valves

4. 6. D.- Relief Valves 1.

When more than one relief valves

1. - Approximate 1y'one-half of' are known to be failed, an all relief valves shall orderly shutdown shall be be bench-checked ~or initiated and the reactor replaced with a depressurized to less than 105 bench-checked valve' psig within 24 hours.

Leach operating cycle. A11 13 valves.will have been checked or replaced upon the completion of every second cycle. 2. In accordance with Specification:1.0.MM,. each relief valve shall be manually opened until. thermocouple and ~ acoustic monitors downstream of the valve indicate steam is flowing-from the valve. BFN 3.6/4.6-10 Unit 2 -~--.n .l.__.. .,, + _,,.,. _..,, _ _, E

--g ' $.6/4.6 BASES 3.6.C/4.6.C.(Cont'd). reasonably in a matter of a few hours utilizing the available leakage detection schemes, and if the origin cannot-be determined in a reasonably short time, the unit should be shut down to allow further investigation and corrective action. The 2 gpm limit for coolant leakage rate increases over any 24-hour-period is a limit.specified.by NRC (Reference 2). This limit applies only during the RUN mode to avoid being penalized for.the. expected coolant leakage increase during pressurization. Thetotalleakagerateconsists.o[a'11. leakage,identifiedand-unidentified.,which flows to the drywell floor drain and equipment drain sumps. The capacity of the drywell. floor sump pump is 50 gpm and the. capacity ofI ~ the drywell equipment sump pump is also 50 gpm.. Removal.of.25 gpm from either of these sumps can be accomplished with considerable margin'. REFERENCE 1. Nuclear System Leakage' Rate Limits (BFNP FSARl Subsection 4.10) 2. Safety Evaluation Report (SER) on IE Bulletin 82-03 3.6.D/4.6.D Relief Valves To meet the safety basis, 13 relief valves have been installed on the unit with a total capacity of 84.1 percent of nuclear boiler rated steam, flow. The analysis of the worst overpressure transient..(3-second closure of all main steam line isolation valves). neglecting the direct scram (valve position scram) results in a maximum vessel pressure which, if a neutron flur scram is assumed considering 12 valves.0PERABLE, results in adequate margin to the code allowable overpressure limit of 1,375 psig. To meet operational design, the analysis of the plant isolation transient' (generator load reject with bypass valve failure to open) shows that 12 of the 13 relief. valves limit peak system pressure to a value which is ~ well below the allowed vessel overpressure of 1,375 psig. Experience in relief valve operation shows that a testing of 50 percent of the valves per year is adequate to detect failures or deteriorations. The relief valves are benchtested every second operating cycleLto ensure that their setpoints are within the 1 i percent tolerance. The relief: valves are tested in place'in accordance with Specification 1.0.MM to establish that they will open and pass steam. BFN 3.6/4.6-30 Unit 2 .e '%m 9 4

---

.-.aa

1 E.. L 3.7/4.7 CONTAINMENT SYSTEMS-' LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE' REQUIREMENTS .' 3. 7. A - -Primary Containment ~ '4.7.'A Primary Containment ) l l 3. Pressure Suppression Chamber '

3. Pressure Suppression Chamber.

Reactor Building Vacuum Breakers Reactor Building Vacuum Breakers'

a. Except as: specified in

a. The; pressure l suppression 3.7.A.3.b below; two. pressure' chamber-reactor. building?

suppression chamber-reactor; vacuum breakers'shall.~bei building. vacuum breakers shall exercised in~accordahce with: be OPERABLE at all-times when. 1.0.MM, andlthe associated. primary containment; integrity . instrumentation including-is required. The'~setpoint setpoint shall:be functionally.' .of.the differential pressure. . tested for proper operation-instrumentation which actuates. each'three-months.1 ' - l the pressure suppression

J chamber-rea'ctor building 1

vacuum bteakers shall be-q 0.5 psi (.

b. From and after the date b.'A visual examination.an'd-1

-that one of the pressure determination-that the suppression chamber-reactor force required.to open'each? building vacuum breakers is . vacuum breaker'(check valve) j made or found to be INOPERABLE does.not exceed.0.5.psid ] for any reason, reactor will be'made each refueling' ) ~ operation is permissible only outage. during the succeeding seven days, provided that the-repair procedure does not q violate primary containment integrity. 4. Drywell-Pressure Suppression

4. Drywell-Pressure Suppression Chamber Vacuum Breakers Chamber Vacuum Breakers

a. Each drywell-suppression

a. When primary containment is

._ required, all drywell-

chamber vacuum breaker' I

suppression chamber vacuum shall be tested in. breakers shall be OPERABLE accordance with and positioned in the fully Specification 1.0.MM. e closed position (except during testing) except as specified in 3.7.A.4.b and 3.7.A.4.c., below.

b. One drywell-suppression

'b.:When it is' determined that-chamber vacuum breaker may two vacuum breakers'are' be nonfully closed so long INOPERABLE for opening ~at a i A BFN 3.7/4.7-10 Unit 2 4*' -49+ m-

• m,.

\\

c s

.g p... .?-. 3

3."7/4.7 CONTAINMENT SYSTEMS-u LIMITING CONDITIONS FOR OPERATION.

SURVEILLANCE. REQUIREMENTS h 3.7.A Primary Containment 4.7.A Primary Containment' l 3.7.A 4.b. (Cont d) 4 7 A.4.b- '(Cont'd) ' j as it l's determined'to be not time when operability is ~ more than.3* open as indicated. required..all.othervacuumi y . breaker valvestshall be by the position lights. exercised:insned!'ately-f and every 15 days;thereafter until the INOPERABLE valve has'been: returned'to normal: service. .j

c. Two drywell-suppression

.c. Each. vacuum breaker valve' chamber vacuum breakers-sha111be_ inspected;for may be determined to be-proper operation of the INOPERABLE for opening. valvetand;11mit switches-g in accordance.with Specification 1.0 NN.: .s

d. If Specifications 3.7.A.4'.a.

d. Al leak. test of the;drywell, j

.b, or c cannot be met, the to suppression chamber q unit shall be placed in a' structure shall be conducted' Cold Shutdown condition in. during each operating cycle. an orderly manner within Acceptable leak rate'is. 24 hours. 0.14 lb/sec of primary. 1 t containment: atmosphere with. l 1 psi differential, a ^ i 5. Oxygen Concentration

5. Oxygen Concentration a.

After completion of the fire-

a. The primary containment related startup retesting program, oxygen concentration >shall containment atmosphere shall be.

be measured and recorded reduced to less than 4% oxygen daily. The oxygen: with nitrogen gas _during reactor measurement sh:11Lbe = adjusted power operation with reactor to account for?the. uncertainty i coolant pressure above 100 psig, of the' method used by adding-except as specified in 3.7.A.5.b. a predetermined error function. b. Within'the 24-hour period

b. The methods.used to measure subsequent to placing the reactor the primary' containment in the RUN mode following a shut-oxygen concentration shall down, the containment atmosphere be calibrated.once'every-oxygen concentration shall be

' refueling' cycle. reduced to less than 4% by volume and maintained in this condition. Deinerting may conunence 24 hours prior to a shutdown. BFN 3.7/4.7-11 Unit 2 j l s ____m__._.__._._. _ _ _ _ _jL_ m

e F 3'.7/4.'7 CONTAINMENT SYSTEMS d LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3.7.A.,

Primary Containment 4.7 A. ' Primary Containment-1 i 3.7.A.S.c' (Cont d) c. If. Specification 3.7.A.'S.a and 3.7.A.S.b cannot be met, anJorderly shutdown shall be- ] initiated and the= reactor shall be in.a-Cold Shutdown l condition within 24 hours. 6. Drywell-Suppression Chamber. .6.'Drywell-Suppression Chamber i Differential Pressure t Differential Pressure o s -- ')

a. Differential. pressure between.

a. The pressure' differentia 1L the drywell and suppression between the drywell'and' chamber shall-be maintained suppression chamberishall at equal to or greater than.

be recordedtat least.once. 1.1'psid except as'specified each' shift.- 1 in (1).and (2) below: 1 \\ (1) This differential shall be established within' 24 hours of achieving-q operating temperature q and pressure. The differential pressure may be reduced to less than 1.1 psid 24 hours prior to a scheduled shutdown. - i i (2) This differential may be decreased to less than 1.1 paid for a-maximum of four hours during required.- operability testing of the HPCI system, RCIC system and the drywell-i pressure suppression chamber vacuum breakers. 3+ l' 3.7/4.7-12l BFN Unit 2 _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _

U, q j-q 5 l 3'.7/4'.7 CONTAINMENT SYSTEMS ] LIMITING CONDITIONS FOR' 0PERATION - . SURVEILLANCE' REQUIREMENTS c 3.768.EStandby Gas Treatment System 4'.7.B.LStandby Gas Treatment i (System, j .3.7;6-(Cont'd). 'b. If the differentia 1Lpressure of Specification 3.7.A.6.a cannot'be-maintained and thef q . differential pressure cannot ~ be restored;within the subsequent six-hour' period,. an orderly; shutdown:shall bei initiated'and the' reactor. shall be'in the:: Cold Shutdown ~ condition within 24 hours.

1. Except as specified in 1.

At~1 east once per: year,; . Specification 3.7.B.3'below,- the following; conditions all three trainslof the shall be1 demonstrated. ~ standby. gas treatment system shall be OPERABLE at alli a. Pressure: drop across the-combined HEPA' times when secondary containment integrity is filters:and: charcoal' l adsorber banks _isLless required. than'6. inches of-water at?a flow of 9000'efm ~ (i 10%)..- ~ .b.: The inlet heaters-on. .each circuit are-tested in'accordance with ANSI N510-1975, and are capable 1of an-output of at!1 east' ~ _.40 kW.. c. Air distribution is uniform within 20%. across HEPA filters and ' charcoal

s adsorbers.

BFN 3.7/4.7-13 Unit 2 nu 6 im ,e )

1 e 3.7/4.7-CONTAINMENT SYSTEMS L LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-L '3.7.C. Secondary Containment- 'i ]

4. If refueling zone secondary.

i. containment:cannot be maintained, th'e following. .jj conditions shall be met: .t

a. Handling offspent fuel land-all operations.over. spent.

l fuel pools'and open, reactor. { wells containing fuel shat 1 1 be prohibited-l

b. The standby gas treatment'

-5 l_ system suction'to the j l-refueling zone will.be blocked except for a- ~ I controlled leakage area { sized to assure the 3 achieving of a vacuum of at least 1/4-inch of' water and not over 3 inches.of water in all three reactor zones. D. Primary Containment Isolation Valves D: Primary Containment Isolation Valves i

1. During reactor power operation,

1. The prim'ary containment I

all isolation valves listed in isolation valves j Table 3.7.A and all reactor surveillance shall be -i coolant system instrument line' performed as follows: l flow check valves shall be OPERABLE except as specified

a. At least'once per in 3.7.D.2.

operating, cycle, the' OPERABLE isolation' valves-I -that'are power operated and automatica11y' initiated shall be tested for simulated automatic. .- initiation,'. and'. in q accordance with-Specification-1.0.MN,- tested for closure ~ times.- l BFN 3.7/4.7-17 l Unit 2 l i

+ ^ w., ^v e .c ' 4.':

f'j l

e t \\ l.\\ \\ l s 7 i [7/4.72 CONTAINMENT SYSTEMSL 3 .,a LIMITING ~ CONDITIONS lFOR OPER TION'- SURVEIL' LANCE' REQUIREMENTS: ~ t' 3.7iD. Primary Containment 4 Isolation. 34.7)D.-hrimaryContainmentIsolation: i ' Valves;'

K Valves 3

i% f4.7;D.I (C'dh'd); o b.-

In accordance~with

Specification 1.0.MM, Call',

-normally open power operated l < : isolation valves ~sh'all bei . functionally testedt, ~' a.. .'c;'Atlleast(twiceper:weekithe'c,, 4 ' mainLateam line, power-operated ' 1{. ~ Isolation valves shallib'e' exercised one.at.-a time bya x r partia10 closure:andTsubsequenti > reopening. Jh y

d. AtEle.ast once;per'operatingg cycleDthejoperabil-ityLof:the?

reactor coolant' system.... Instrument line" flow checki valves;shall.betverified.

2. In the event'any isolation valve

2. Whenever<an: isolation;. valve specified in Table 3.7.A becomes

listediin Table 3.7. asis.

INOPERABLE,-the; position ofcat.-

INOPERABLE, reactor power. 11 east one other' valve.!in"e'ach operation may continue provided. ~ at least one valve in each line line:having.an' INOPERABLE valve: having an~ INOPERABLE valve'is in shallibe. recorded daily.- M. the mode corresponding to the-isolated condition. ' d, -- i q 3.-If Specification 3.7.D.1 and .j 3.7.D.2.cannot be met.-an ~ orderly shutdown shall be-initiated and the reactor shall-be-in the Cold Shutdown condition 1 a within 24 hours.- i b I "t i i ( .j

\\

BFN- -3.7/4.7-18 j q . Unit 2 r ) Jr y;, i 7: ___.=_:_2. -.L :. _ j ?

4 .c . <. j --~---q so ?- 6 3.7/4.7J: CONTAINMENT SYSTEMS .. LIMITING CONDITIONS FOR OPERATION . SURVEILLANCE' REQUIREMENTS pt. 3.7.G. Containment Atmosphere-4.7.G. Containment' Atmosphere l.' . Dilution System (CAD) 1 Dilution System (CAD). l'. .The Containment Atmosphere 1. System Operability Dilution (CAD) System shall ,ml '? ' be OPERABLE with: J' . g'd a'. Two independent . a '. Cycle"each solenoid systems capable of; ,{- operated. air /nitrogenJ

supplying nitrogen' valve through at to the drywell and least one: complete cycle of full traveli 4 4

torus. in accordance with-,# ', Specification'1,0.MMy

aad:at least.once per7 month; verify that each-manual' valre 'in' the -

fliv path is open.. b.'A minimum supply of b. Verify thattthe[ CAD 2,500 gallons of System conts. ins.a: liquid nitrogen per minimum b gply of-system. 2,500 gallons.of, ligdid nitrohen N, ' twicelper weeks. / y 't 2. The Containment'Atmosphero _ 1 i Dilution (CAD) System shall! l be OPERABLE whenever the reactor mode switch is in l the "RUN" position. l 3. If one system is INOPERABLE, the reactor may remain in operation for a period of a 30 days provided all active components in the other system are OPERABLE. a ' i,. L'L i ]F r / ?. ( BFN 3.7/4.7-22 ~ p '"J d_ Unit 2 u kf M( i c y ..N, $u%j w,,., .~.

3.7/4.7 BASES (Cont'd) Groups 4 and 5 - Process lines _are designed to remain operable and mitigate ')' ^ the consequences of an accident which results in the isolation of'other y-process lines. The signals which initiate isolation of' Groups 4 and=5 process lines are therefore indicative of a condition which would render them -inoperable. g Group 6 - Lines are connected to the primary containment but not.directly to Q the reactor vessel. These valves are isolated on reactor low water level e (538"), high drywell pressure, or reactor -building ventilation high radiation which would-indicate a possible accident and necessitate. primary containment' isolation. I Group 7 - Process lines.are closed only on the respective turbine' steam supply valve not fully closed. This' assures that the' valves are not open when HPCI or RCIC action is required. Group 8 - Line (traveling in-core probe) is isolated on high drywell pressure 'l / or reactor low water level (538"). This is to assure that this line does not-fj provide a leakage path when containment pressure or' reactor. water level' indicates a possible accident condition. f The maximum closure time for the automatic. isolation valves of the primary containment and reactor vessel isolation control system have be'en selected in consideration of the design intent to prevent core uncovering following pipe l breaks outside the primary containment and the need to contain released. ~ fission products following pipe breaks inside the primary containment. j In satisfying this design intent, an additional margin has been, included in specifying maximum closure times. This margin, permits identification of degraded valve performance prior to exceeding the design closure times. j In order to assure that the doses that may result from a steam line break do not exceed the 10 CFR 100 guidelines, it is necessary that no fuel rod perforation resulting from the accident occur prior to closure of the main i steam line isolation valves. Analyses indicate that fuel rod cladding ) perforations would be avoided for main steam valve closure times, including instrument delay, as long as 10.5 seconds. i normally closed. The initiating sensors and associated trip logic are also '.1 These valves are highly reliable, have low. service requirements, and most are checked to demonstrate the capability for automatic isolation. The test Y 4 interval of once per operating c cle for automatic initiation results in a failure probability of 1.1 x 10-that a line will not isolate. More frequent testing for valve operability in accordance with Specification 1.0.MM { results in a greater assurance that the valve will be cperable when needed. The main steam line isolation valves are functionally tested per Specification 1.0.MM to establish a high degree of reliability. The primary containment is penetrated by several small diameter instrument lines connected to the m actor coolant system. Each instrument line contains i' a 0.25-inch restricting orifice-inside the primary containment and an excess-flow check valve outside the primary containment. ,t ,l BFN 3.7/4.7-50 Unit 2 3

y c n. =- r-u of: L \\ [$NDEFINITIONSi(Cont?d)I' E 's-W 3; j[ MM L Surveillance requirements =for ASME-SectionJXI Pump and Valvei, 'g Program:. Surveillance: requirements:for-Inservice: Testing;of-1 ASME CodeLClass:1,;2i andl3lcomponentsjshall be: applicable.as* ? follows: l'. jInservibttestingforASME;CodeClassII,2,and'3'.-pumpsan( J' ' valves shall:be performedsin'.accordance with Section XI of-- f the?ASME Boiler and; Pressure Vessel Code _and applicable. l/f 3 N a li ' Addenda asirequ!idM byLIO CFR 50,iSection 50.55a(g), exceptL ?u 7 where speci,firjuritten relief'has been' granted by..the [ 1 j . Conseis'sion pursuant to 10 CFR 50, Section 50.5Ea(g).(6)(i). n 1 f. m Surveillance, intervals specified~in Section XI"of.the'ASME

2.. Boiler:and Pressure Vessel code and applicable fddenda for:

.g the inservice 'er, ting activities required byL the ~ ASME Boiler; ,s and Pressure; Vessel Code and? applicable.Adden d shallibel applicab1'e as Collows :in 'these technical, specifications: ~ ,r l 'ASME Boiler an'd; Pressure Vessel. ?' i I t . Required frequencies _ i .\\ s Code and applicable Addenda- 'for performing' inservice terminolsfy for inservice ' testing' activities testing setivities _1 op j s 1 ~

r,At~1 east once per 7, days-Weekly-7

+ .l MonthlyL . / ~ At least once.per 31'. days; 4 . Quarterly'or'every 3 montht!: 1J At.least-onceLper 92? days' Semiannually or every 6 months. At least once per 184Ldays.. 1 Every 9 months. At'least,once per 276 days;> Yearly or annually lAt~1eastionce per 366Ldays ,fj M u 3. The provisionsiof Specification 1.0.LL are applicable to the:- O atiove required frequencies for performing [ inservice testing; activides ,( 4. Performance of the above inservice testing.-: activities.shall be in ' addition to-otlner specified ' surveillance requirements.. l 4i

5.

Nothing in the ASMF Boiler and, Pressure Vessel Code shall,be-g .I ' construed to supercede the requirements of'any: technical specification. ~ ^?C t i 1, ,~ a 7

j. -

.J ne n. T .[' j ] ~ c J BfN g / nit 3 11.'0-12 U 7 r v.. f 4 v e 4 q t. -~..f, .j 4.. } ,g

_ z.

- is ~ W A-_ _ L_.

.o. j 'u e l s . Table 1.p . i SURVEILLANCE-FREQUENCT NOTATION 4 q -NOTATION.

• l FREQUENCY S

(Shift) At.least once per 12 hours'. D (Daily) At least-once per normal calendar 24 hour dayf(midnight to midnight). W (Weekly ). At least once per;7fdays. 1 M (Monthly)

At least once per 31 days.

Q' (Quarterly). 1At least once'per 3 months.or 92 days; SA (Semi-Annually) lAtLleast once per'6 months or 184 days. 1 Y (Yearly) At least once per year or 366 days, j R .(Refueling) At Idast once per.operatingLeycle. 1 S/U (Start-Up) Prior to each reactor startup.- N.A. Not applicable. P (Prior) Completed-prior to each release. 1 BFN Unit 3 1.0-13 i

3.3/4.3 REACTIVITY CONTROL LIMITING CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.E. If. Specifications 3.3.'C and 4. 3 ' E., Surveillance requirements are-as.specified in 4.3.C and' 3.3.D above cannot be inet,-. '4.3)D'above. an orderly shutdown shall be initiated'and the reactor-shall be in the Shutdown condition within 24 hours. F. Scram Discharge Volume (SDV). F. Scram Discharr.e Volume' (SDV) 1. The scram discharge volume 1.a..The scramidischargel drain and vent valves shall volume drain.and vent' be OPERABLE any time that ' valves shall be; verified the reactor protection' Lopen prior to each system is required to be -startup and monthly: l OPERABLE except as thereafter. The valves l specified in 3.3.F.2. may be-closed- ) . intermittently for ' testing not to exceed" I hour.in any 24-hour' l period during operation. l 1.b. : The scram discharge volume drain and vent' valves shallibe. I demonstrated OPERABLE ( in-accordance with Specification-1.0.MM. j 2. In the event any SDV drain 2. When it'is determined or vent valve becomes 'that any SDV drain or. INOPERABLE, reactor vent valve is INOPERABLE, operation may continue the redundant. drain or. -l provided the redundant vent velve shall be drain or vent valve is-demonstrated OPERABLE OPERABLE. immediately and weekly .thereafter.. 3. If redundant drain or vent 3. No additional valves become INOPERABLE, surveillance required. the reactor shall be in Hot Standby within 24 hours. BFN Unit 3 3.3/4'.3-11 a

i

• n e

<i 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 ' STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY. LIQUID CONTROL SYSTEM Applicability' Applicability Applies to the operating status Applies to the surveillance. of the Standby Liquid Control. ' requirements of the Standby System. l-Liquid Control System. ~ Objective Objective To assure the availability of a To verify the operability'of-the system with the capability to. Standby Liquid Control System.. shut down the reactor and maintain the Shutdown Condition without the use'of control rods. Specification Specification A. Normal System Availability A. Normal System Availability 1. The Standby Liquid Control The operability of the Standby System shall be OPERABLE Liquid Control System shall be at all times when there verified by the performance is fuel in the reactor of the following tests: vessel and the reactor is not in a Shutdown condition

1. -Verify pump operability with all OPERABLE control in accordance with-rods fully inserted except Specification 1.0.NM.

as specified in 3.4.B.1. 2. At least once during each operating cycle: a. Check that the setting of the system relief valves'is.1,425 1 75 psig. ~ b. Manually initiate the. system, except explosive valves. pump boron l solution through the l recirculation path and back to.the Standby. Liquid Control Solution Tank. Minimum pump flow rate of 39 spm against a system head of 1,275 psig shall be verified. BFN Unit 3 3.4/4.4-1 l

uI t i e '1 ' 3.4/4.4' STANDBY LIQUID CONTROL' SYSTEM: LIMITING CONDITIONS FOR~0PERATION SU VEILLANCE' REQUIREMENTS 4 'Ndrma1 SystNm Applicability: I 4 4. AT 2 s 4'. 4 ; A. 2. b1(' Con t ' d)l, j After pumping boronc q. ; ! solution,.the system:shall? ':.6d 'be flushed with-demineralized water. - 1. Manually. initiate oneio'f_.the - i c.. Standby: Liquid Control' -System' loops land pumpf. . demineralized. water into the: reactor vessel.' y3 This test check's explosion D of:the charge assoca<ted .with the tested loopRpropern . operation of;the: valves,;and; pump; operability.1 Replacement charges 3shallibe: selected suchLthat'the_ age; of: charge in service ~shalli not ' exceed' five years : from : the manufacturer's assembly date. ~ d. Both systems.: including both . explosive;. valves,'shallt be ~ ~ tested in:the course of>two operating cycles. B. Operation with Inoperable B. -Surveillance with Inoperable Components Components-1. From and after the date

1.. When a' component' isifound -

that a redundant component to be INOPERABLE,.its is made'or found to tua - redundant-component shallt INOPERABLE, Specification 'be: demonstrated to be' 3.4.A.1 shall be considered OPERABLE'immediately1and' fulfilled and continued dailyLthereafter'until the operation. permitted INOPERABLE component isL provided that the. repaired., 'c ' component is returned to an OPERABLE condition within seven days. BFN Unit 3 3.4/4.4-2 ~ O M _-,___-- _ - ~_.-_w-----,_______.,___.____--_.-_,.-_------___--_--____-_-_-______---_-._._ x a- --___._______-___._-_-_.--_.a_

. 0,.1 w 4 y 2 ?3.S/4.5L-CORE AND' CONTAINMENT COOLING SYSTEMSi V u q: j l LIMITING' CONDITIONS FOR-OPERATION SURVEILLANCE REQUIREMENTS. 1 ~ 3.5. CORE AND CONTAINMENT COOLING. '4.5: CORE AND CONTAINMENT C00 LING-- SYSTEMS-- ' SYSTEMS Applicability ~ Applicability-App 11'es to the operational -Ahplies'to't$ surveillance ] ~ status of the Core and"

requirements offthe: Core andJ Containment Cooling-Systems.

-Containment; Cooling' Systems.when1 ~ the'correspondingslimiting condi-1 1 tion for-.operationEls'in.effect. l Objective-Objective ~ y 1-To assure the operability of 'To verify the operability.of;thel 'l i the Core and Containment Cooling: -Core and: Containment Cooling;. Systems.under all conditions for- . Systems;under,all1 conditions for R which this cooling capability is. -which this coolingjcapability is; lj l~ abnormalities, abnormalities.. ]f an essential response to plant an essential: response to plant ~- 8. ( Specification Specification- ] A. Core Spray ' System (CSS); A. Core Spray System (CSS) 1. The CSS shall be OPERABLE: 1, 1 Core SprayfSystem~ Testing. 4 l E . Item

Frequency j

l (1) prior to reactor d startup from a Cold Condition, or a.. Simulated Once/ Aut'omatic = Operating (2) when there is irrediated ' Actuation. Cycle fuel.in the vessel testi j and when the reactor vessel pressure

b.. Pump Opera-- iPer Specifi

~ is greater than .bility' cation 1'.0.MM. atmospheric pressure. ._Per.Specifi. j except as specified c. Motor ~ in Specification Operated' cation 1.0.MM i 3.5.A.2. Valve Operability d. System flow Once/3' rate: Each months' l loop shall 3 deliver at least 6250 gpm against .j a system' head corres-' a 't ponding to:a BFN' Unit 3 3.5/4.5-l' ,) i s

~, _ aji

i. -

r r -l 3. 5 / 4 ~. 5 2 CORE AND CONTAINMENT'COOLINGiSYSTEMS ' 4 l LIMITING CONDITIONS FOR OPERATION-

SURVEILLANCE REQUIREMENTS:

l 3.5.A core Spray System (CSS) 4.5.A Core Spray" System (CSS)l ? 9 4.5.A.1.d (Cont'd) Y 3 105 psi -differential ~ i pressure = between the. reactor vessel and the primary ~ s containment.

e... Testable.

Per h Check Valve. Specification i' 1.0.MML y 2. If one CSS loop is INOPERABLE, 2. When it is ' determined that: one 1 'l the~ reactor may remain.in-core sprayiloop is' INOPERABLE,' t i operation for a period not to-- at a' time when' operability is' ~ exceed 7 days providing- -required, the othericore' spray. .j :, all active components.in

loop, theLRHRS1(LPCI mode),Jandl 4

the other CSS loop and the the; diesel generatorsPshall be? j RHR system-(LPCI mode). ' demonstrated'to be OPERABLE and the diesel generators immediately. The 0PERABLE. core: j

are OPERABLE.

spray loop'shall be. demonstrated. ,to be OPERABLE dilly thereafter.. i .)

]

3. If Specification 3.5.A.1 or. Specification 3.5.A.2 cannot H be met, the reactor shall be shutdown in the Cold l Condition within 24 hours. l 4. When the reactor vessel 4 pressure is atmospheric and i irradiated fuel is in the { reactor vessel, at'least one J core spray loop with'one l OPERABLE pump and associated' diesel generator.shall be OPERABLE, except with the i reactor vessel head removed-as specified in 3.5.A.S.or prior to reactor startup as l specified in 3.5.A.1. 'I l ~I BFN Unit 3 3.5/4.5-2. / .j l l ~-. f.. N t. a .i.____.i_'__li_i_. _______.___.__.____._._.._.l._..m.

m ".5/4.5 ~ CORE AND CONTAINMENT COOLING SYSTEMS ; LIMITING CONDITIONS FOR OPERATION-SURVEILLANCE REQUIREMENTS-3.5.B Residual' Heat Removal System 4.5'.B.' Residual Heat Removal System (RHRS)-(LPCI and Containment: (RHRS) (LPCI and' Containment. Cooling) Cooling). -1. The RHRS shall be OPERABLE:

1. a'.

Simulated .Once/-. 1 Automatic Operating-Actuation. Cycle; (1) prior'to a reactor .startup from a Cold' ' Test' Condition, or .( ) (2) when there is 'b. Pump'0pera-Per Specifi-irradiated fuel in bility. tion 1.0.MM the reactor ~ vessel j and when the reactor vessel. pressure is-c. Motor Opera-Per.'Specifi-greater than. ted valve. cation 1.0.MM atmospheric,iexcept as ~ operability j specified in ] Specifications 3.5.B.2, d '. Pump Flow' Once'/3h i through 3.5.B.7. Rate . months e. Testable. Check Per = Valve Specification 1.0.MM Each LPCI pump.shall' deliver 9000 gpm against.. 'an indicated system pressure of'125 psig.- Two LPCI pumps in the'same l loop sha11Edeliver 12000 l gpm against anLindicated system pressure of 250 l psig. j i 2. With the reactor vessel

2. An air test on'the drywell

) ~ pressure less than 105 psig, and torus headers and nozzles i the RER may be removed shall be conducted once/5 j from service (except that two' years. A water test may'be' RHR pumps-containment cooling performed on the torus header mode and associated heat in lieu of the air t0st. exchangers must remain OPERABLE) for a period not to ~ exceed:24 hours while being ( drained.of suppression chamber L quality water and filled with l primary coolant quality water, provided that during'cooldown j two loops with one pump per. I loop.or one. loop with two pumps, and associated diesel generators, in the core spray 1 system are OPERABLE. .j BFN i Unit 3 3.5/4.5-4

'3.5/4.5 CORE AND ' CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATJON SURVEILLANCE REQUIREMENTS 3.5.B1 Residual Heat Removal System 4.5.B Residual Heat Removal System (RHRS) (LPCI and Containment (RHRS) (LPCI and-Containment' Cooling)(Cont'd) . Cooling)(Cont'd)

8. If Specifications 3.5.B.1 ~

8. No' additional surveillance-through 3.5.B.7 are not mat,

required, L

an orderly shutdown shall be q initiated and the reactor shall be shutdown and placed in the Cold Condition within 24 hours.

9. When the reactor vessel

9. When the reactor vessel-pressure.is atmospheric and pressure-is atmospheric, irradiated fuel is in the the RHR pumps and valves reactor vessel, at least one RHR that are required to be l

loop with two pumps or.twoLloops OPERABLE'shall be l with one pump per loop shall- -demonstrated to be OPERABLE be OPERABLE. The pumps' 'per Specification 1.0.MM. l associated diesel generators must also be OPERABLE. q 1 10. If the conditions of

10. No additional surveillance-

'f Specification 3.5.A.5 are met, required. J LPCI and containment cooling ] are not required, j i 11. When there is irradiated. fuel

11. The B and D RHR pumps-on

) in the reactor and the reactor unit'2 which' supply vessel pressure is greater than cross-connect capability-atmospheric, unit 2 RHR pumps B shall be OPERABLE 3 and D associated with heat ex-monthly when the changers and valves must be cross-connect' capability OPERABLE and capable of is. required. I supplying cross-connect capability except as specified in Specification 3.5.B.12 below. (Note: Because cross-connect capability is not a short-term requirement, a component is not considered - INOPERABLE if cross-connect capability can be restored to service within 5 hours.) BFN Unit 3 3.5/4.5-7 e

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION : SURVEILLANCE REQUIREMENTS i 3.5.C RHR Service Water and Emergency

4. 5.C - RHR Service Water and-Eauipment Cooling-Water Systems Emergency Equipment Cooling; (EECWS)

. Water Systems (EECWS)

1. Prior to reactor.startup from 3.

a. Each'of the RHRSW pumps a Cold Condition, 9 RHRSW normally, assigned to pumps must be OPERABLE, with ' automatic service'on 7 pumps (including pump B1 the EECW headers will-or B2) assigned to RHRSW be tested. service and 2 automatically automatically-each time starting pumps assigned to the diesel generators EECW service. are tested. Each of the RHRSW pumps and all associated essentia11 control valves for the-EECW headers and RHR heat' exchanger headers shall be-demonstrated to be OPERABLE in accordance - with Specification 1.0.MM. b. Annually each RHRSW pump-shall be flow-rate tested. To be considered OPERABLE, each pump shall-1 pump at least 4500 spm, j through its normally. l i assigned' flow path. 1 i i l l 2 l -I l l BFN Unit 3 3.5/4.5-9 i L- '1

a e 5 i t .-.4 -3.5/4.5 -CORE'AND' CONTAINMENT COOLING' SYSTEMS: .:) LIMITING CONDITIONS ~FOR OPERATION? SURVEILLANCE = REQUIREMENTS j -3,5.D Equipment Area' Coolers '4.5.D. lEauipment' Area Coolers, V '1.'The equipment area cooler '3. !Each equipment area' cooler-i ji' associated withleach RHR .is operated in conjunction d t l pump and the equipment- .with the:equipmentiserved!~ . area, cooler-associated 'by that:particular cooler; with'each set of' core .therefore, thefeguipment;

sprayipumps (A and C

-area coolersiare: tested'at the.same' frequency.as;the- 'or B and.D)'must be; ' l pumps which theyLserve. l. OPERABLE.at a111 times. t when the pump or. pumps l L served.by that specific-cooler is. considered-to .be OPERABLE. l L

2. When an equipment. area cooler is not 0PERABLE,..

] the pump (s) served by!that cooler must be considered INOPERABLE for technical a-

j

~ specification purposes. E. High Pressure Coolant Injection 'E. High Pressure Cool' ant System (HPCIS)

Injection System (HPCIS)'

i 1. The HPCI system shall be

1 =..HPCI: subsystem! testing OPERABLE:

'shall be performed as i follows: (1) prior to startup-from-a -a. Simulated- '. Once/ a Cold Condition, or Automatic operating- .Actu' tion cycle a Teste .b. Pump lPer: (2) whenever there is. irradiated fuel in the Lopera-' Specification- ~ reactor vessel'and the

bility 1.0.MM?

j reactor vessel pressure is greater than 122 psig, 'c. Motor Oper-

Per-..

sg" except as specified in. .ated Valvei Specification. Specification 3.5.E.2. . Operability. 1.0.MN,

d. 1 Flow Rate-at -Once/3 normal" months-L' reactor

-vessel' operating pressure:: BFN Unit 3 - 3.5/4.5-13 u.

. 3.5/4.5 CORE AND CONTAINMENT'C00 LING SYSTEMS LIMITING' CONDITIONS FOR OPERATION- ' SURVEILLANCE REQUIREMENTS. j 3.5.E High> Pressure Coolant Injection 4.5.E !High Pressure Coolant: System (HPCIS) Injection System (HPCIS)' 4.5.E.1' ( Con t d ) 'l e. Flow Rate at Once/.. ' operating' 150 psig.' icycle~ TheIHPCI pump.sh'all deliver' 'at least 5000.gpm during- 'each flow rate > test. ~ 2. When it is determined that. .2. If the HPCI system is, ~ the HPCIS is INOPERABLE,,the INOPERABLE, the reactor may remain in operation forfa: ' ADS actuation' logic,'the. period not to exceed 7 days, -RCICS, tfe~RHRS (LPCI),'and provided the' ADS, CSS 'RHRS the CSS shall be (LPCI), and RCICS are ' demonstrated to be OPERABLE i OPERABLE. immediately. 'The RCICS and ADS' logic'shall be demonstrated. [ to-be OPERABLE daily thereafter. 1 3. If Specifications 3.5.E.1 i or 3.5.E.2 are not met'- l an orderly shutdown shal1~ be initiated and the reactor vessel pressure shall be reduced to'122 psig or less within 24 hours. F. Reactor Core Isolation Cooling F. Reactor Core 1 Isolation Cooling System (RCICS) System-(RCICS) 1. The RCICS shall be OPERABLE: 1. RCIC-Subsystem testing shall be performed as follows:- (1) prior to STARTUP from a Cold Condition, or a.' Simulated-Once/ Automatic operating (2) whenever there is Actuation Test. cycle irradiated fuel in the Per Specifi-j reactor vessel-and the

b. Pump 1 cation 1.0.MM reactor _ vessel pressure Operability.

is above 122'psig, except as specified in

c. Motor-Operated Per 3.5.F.2.

Valve' Specification' Operability 1.0.NM BFN Unit 3 3.5/4.5-14 / w 4 A_a__,__ _ _ _ - - - - -, -.. - - - _. - -.

l Ji e ~ A SL ' Core and; containment'Coolint Systems Surveillance Frequencies. ~ ,The testing' interval for the core.and: containment"co ding.'systemslis 1 ~

based on industry practice, quantitative reliability analysis,wjudgment,-

and practicality. The' core cooll'ngssystems have nott..been designed to be . fully testable during" operation; JF6r example, in theLease'of the.HPCI,' ,i automatic initiation during pow 4r_ operation would resultiin'p' umping cold; water into the reacter vessel which:is not desirable'. ' Complete ADS l testing-during; power operation causes an undesirable loss-of-coolantV Oj !t inventory..To: increase 1theTavailability of the.-core and! containment cooling system,Lthe components!which makeLup'the. system,Li.e., instrumentation, pumpsW valves,Letc...are tested (frequently? cTherpumps. N and motor operated injection valves are 'also tested in accordance withi ? ~ Specification 1.0.MM to. assure.their operability. : A simul'at'ediautomatic 0' actuation test ~once each cycle combined with' testing of pumps and-1 . injection valves.in accordance with Specification _1.0.MM is deemed to be L( t adeguateitesting of these-systems, 4 When components and subsystems;are out-of-service,Loverall. core:and'- ' i containment cooling. reliability is. maintained byl demonstrating the r operability'of the remaining' equipment. The degree'of operability to;be. demonstrated depends =on the-nature of the reason'for the out-of-service: 1 equipment. Forjroutine out-of-service periods. caused:by preventive j maintenance,;etc.,'the= pump and. valve. operability checksLwill be performed to demonstrate _ operability?of tho' remaining components.- i However, if a' failure,: design ~ deficiency, cause the outage, then the' demonstration of. operability should be. thorough enough to' assure that a.. 1 generic problem does not exist. fFor example,'if an out-of-servicelperiod. was caused by failure!of a pump to deliver' rated capacity due toca design deficiency, the other. pumps.of thi's type'might'be subjected ~to a flow-rate test in~ additionito the ~ operability checks. J j Whenever'a CSCS system or-loop'is made_ INOPERABLE because ofla required .i test or calibration,-the.other CSCS systems or loops that-are requ! red to: l be: operable'shall be considered OPERABLE if-they_'are within the required ~ surveillance testing frequency 'nd;there is no reason'to suspect they are: i a INOPERABLE. If.the function, system,sor loop under-test or: calibration is found INOPERABLE or exceeds the trip level setting', the LCO'and the a required surveillance testing for;the, system orLloop shall apply; l Redundant OPERABLE components'are' subjected to: increased testing'during equipment out-of-service times.. This~ adds further conservatism:and' increases assurance that adequate cooling is available should the need arise. Naximum Average planar LHGR. LHGR.'and MCpR The MApLHGR, LHGR,_.and MCPR shall-be checked daily to determine if fuel burnup or control rod movement'has; caused changes =in power distribution.' Since changes due to.burnup'are. slow,'and.only-a few control' rods are moved daily, a daily check of power _ distribution is; adequate.

l a

BFN Unit 3 3.5/4.5-36 / i n_.. '

4; 7,if ,.: 3 r r o, r. j ,e

3..6/4.61-PRIMARY ^ SYSTEM' BOUNDARY.

TLIMITING: CONDITIONS FOR. OPERATION SURVEILLANCE" REQUIREMENTS? .3.6.C; Coolant Leakage-4. 6 '. C l CoolantL Leakage' L -2L Both:the sump and air sampling' l2.. Olth the air sampling . systems shall be 0PERABLE during system.INOPERABLEEgrabi reactor power-.; operation.;. From.-' < samples;shall;be obtained6 'and after the;date.that one'ofJ- - and ' analyzed Jat ' lea's ti once : ]f these systems is made or fou'nd 'every 24 hours., j to be INOPERABLE foriany reason, reactor-power operation is1 permissible only:during;the. ll 1 succeeding 72 hours.

\\

J The air sampling system may

3 p'

~ j be removed from service for a .r period of.4' hours for< . calibration, functional testing, and maintenance without 1 providing a temporary .3 monitor. 3. If the condition in 1 or.2 I

• above cannot be met..an orderly-

- f' <-. .2 shutdown shall be initiated-I i i and the reactor shall be-shutdown in the Cold Condition within 24 hours. l '4.6.D. Relief < Valves 3.6.D. Relief Valves .1. Approximately:one-half'of! j 1. When more than one relief valve is known to 'be f ailed, an .all relief,valvestshall-q orderly shutdown'shall be' 'be: bench-checked:or 1 initiated and the reactor . replaced with'a ';l depressurized to less than.105 ' bench checked: valve: psig within 24 hours. 'eachfoperating cycle.

A11.131 valves;willlhave'

.been checked orLreplaced l upon-the completion of: l-every 'secondLeycle. l I 2. InLaccordance with: i - Specification L 1.0.10f, ~ l L each' relief; valve'shall I .be manually. opened.until' -thermocouple;and acoustic' monitors: downstream of the valve?

indicate steam'.is..

j L .flowingLfrom the valve. y BFN Unit 3 3.6/4.6.j 1 --s W, s

r ~3.6.C/4.6.C (Cont'd)- 1-reasonably in a matter of a few hours utilizing the available leakage. _ .j detection schemes, and if.the origin'cannot.be determined in:a. reasonably short time, the unit should be shut down to' allow further investigation,andf corrective action. 4 The two gpm limit for coolant leakage rate increase over any 24 hour..perio'd is a limit specified by'NRC (Reference 2). This limit applies only.during the RUN mode to avoid being penalized;for the expected coolant' leakage increase.. j during pressurization, -l 1 The total leakage rate consists of all leakage, identified and unidentified, which flows to the drywell floor drain and equipment drain' sumps. The capacity of the drywell floor' sump pump is 50 gpm and the capacity of the 1 drywell equipment sump pump is also 50 gpm. -Removal of.251spm from either.of these sumps can.be' accomplished with considerable margin. { References Nuclear System Leakage Rate Limits (BFNP FSAR Subsection 4.10) 1. 2. Safety Evaluation Report (SER) on'IE-Bulletin 82-03 3.6.D/4.6.D Relief Valves ~ -' To meet the"~ safety basispl3 relief-valves have been' installed on. the unit _ __.. with a total capacity of.83.77 percent of nuclear boiler rated steam flow. The analysis of the worst-overpressure transient,-(3-second closure of~all ~ main steam line isolation valves) neglecting the direct scram (valve position-1 scram) results in a maximum vessel pressure which -.if a neutron'fluz scram is l assumed considering 12' valves OPERABLE, results'in adequate' margin'to the' code-allowable overpressure limit of 1,375 psig. To meet operational design,~-the analysis of the plant isolation = transient (generator load reject with bypass valve' failure to open) shows that 12 of the 13 relief valves limit peak system pressure to a value which~is well-below the allowed vessel overpressure of 1,375 psig. Experience in relief aYid safety valve operation shows that a testing of 50 percent of the valves per.. year is adequate to. detect failures'or. deteriorations. The relief and safety valves are benchtested every:second operating cycle to ensure that their setpoints are within the 1 I percent tolerance. The relief valves are tested in place in accordance with Specification 1.0.MM to establish that they will open and pass steam. 1 BFN 3.6/4.6-30 Unit 3 l i 1 4

/ ; ' W e, g 3 7/4'.7 CONTAINMENT SYSTEMS: LIMITING ~ CONDITIONS FOR,0PERATION' ' SURVEILLANCE ; REQUIREMENTS y l :- '4.7.A;gRIMARY CONTAINMENT { l 3. 7.. A'. PRIMARY 2 CONTAINMENT 3. Pressure Suppression' Chamber - E3. Pressure Suppression' Chamber - Re_ actor Building Vacuum Breakers'

Reactor Building Vacuum' Breakers p

l-4 a..Except as specified in a.Thefpressuresuppressioni 3.7.A.3.b below, two pressur'e chamber-reactor buildi.ng: vacuum. breakers shall'be: suppression chamber-reactor

exercised in accordance witit'

~ building vacuum.. breakers shall' be OPERABLE.at all times.when! Specification 1.0.MM,Tand the-l primary containment integrity. ! associated instrumentation 7, is required. The-setpointL7 including'setpointlshall be? of the differential-pressure

functionally _ tested' for!

instrumentation which_ actuates' proper operation _each three-the pressure _ suppression' months.- chamber-reactor,buildingi vacuum breakers'shallibe-0.S'psid. s

b. From and after the,date

'b'.' A: visual examination.and' that one of the pressure - - determinationLthat thel.. t suppression chamber-reactor . force required to;open each building vacuum breakers is _ ..' vacuum breaker - ( check. v'alve )- does not exceed 0.5Lpsid-made.or'found to be INOPERABLE- ~ will be made'each refueling for any reason, reactor-operation is permissible only outage. during the succeeding'seven days, provided that the repair procedure does not violate primary containment. 4 integrity. 4. Drywell-Pressure Suppression.

4. Drywell-Pressure Suppression Chamber Vacuum Breakers Chamber Vacuum Breakers.

a. When primary containment is a.'Each drywell-suppression required, all drywell-

chamber vacuum breaker suppression chamber vacuum shall be tested'inL breakers shall be OPERABLE accordance with and positioned in the fully Specification.110.MM.

I l. closed position (except-- during testing)'except'as specified in 3.7.A.4.b and R 3.7.A.4.c below.

b. One.drywell-suppression b.'.When it.is determined'that:

chamber vacuum. breaker may two'vacuumLbreakers'are l be nonfully closed so long INOPERABLE for opening'.at.a' ^ l 4 l ' BFN 1 Unit 3-3.7/4.7-10 l l l l g

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y lr q 3.7/427: CONTAINMENT SYSTEMS: LIMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS- '3.7iA -Primary Containment' f4.'7'.A Primary Containment. 33.7;A.4.b -(Cont'd); 4.7.A.4.b7 (Cont'd)" - w, timewhenoperability/3s' as it is determined to be'not., -more than 3*Lopen as indicated. ' required, alliother? vacuum-by the position lights. breaker! valves?shal14be. exercisedilmmediately:and every-L15 l days thereaf ter.dntil :the ' INOPERABLE ; valve has been : . returned to. normal' service.

c. Two drywell-suppression

'c. Each vacuum. breaker valve chamber vacuum breakere shall be. inspected for may be determined to be proper' operation"of the. s INOPERABLE for opening, svalve and limit switches -in accordance with' Specification 1.0.MM.

d. If Specifications 3.7.A.4.a.

d. A. leak' test of the_drywelli

^ 3.7.A.4.b, or 3.7.A.4.c. .to suppression chamber' l ~ - 'cannot be metr the structure shall;be conducted; unit shall'ba placed 1during each. operating cycle.^ .in a Cold Shutdown Acceptable leak rate is-condition in an orderly. 0.14'1b/see of primary. manner within 24 hours. containment. atmosphere withi i psi differential. i 5. Oxygen Concentration

5. Oxygen: Concentration'

.( l a. After completion of the 300-hour

a. Thel primary. containment warranty run, containment

. oxygen: concentration shall 1 atmosphere shall be reduced be measured'and recorded to less than 4% oxygen with daily.3:The. oxygen 1 nitrogen gas during reactor measurement shall be adjusted to account'for;the: uncertainty 7 l power operation'with reactor coolant pressure above 100 psig, of the method used by: adding: except as specified in 3.7.A.S.b. a predetermined' error function.: .] b. Within the 24-hour period tu The. methods used to measure z subsequent to placing the reactor -the primary containment in the RUN mode following a shut-oxygen' concentration'shall" down the containment atmosphere. be calibrated once every oxygen concentration shall be' refueling cycle. reduced to less than 4% by volume and maintained in this condition. Deinerting may commence 24 hours prior to a shutdown. BFN Unit 3 3.7/4.7-11

'j ,o: 3'.7/4.7 CONTAINMENT SYSTEMS' i SURVEILLANCE REQUIREMENTS' LIMITING CONDITIONS FOR OPERATION 4.7.A. Primary ~ Containment? 3.7.A. Primary: Containment 3.7.A.5.C (Cont'd) If the specifications of c. '3.7. A. 5~. a. through. 3.7. A. 5. b cannot be met, an orderly shutdown shall be: initiated and the reactor.shall be in a Cold Shutdown condition within 24 hours.- 6. Drywell-Suppression Chamber _'

6. Drywell-Suppression Chamber-

)

Differential Pressorec Differential Pressure -{

a. Differential pressure between

a. The' pressure differential L

the drywell and suppression between'the drywell_and, 'j chamber shall be maintained suppression chamber:shall: ~be recorded at.least once. at equal to or greater than each shift. 1.1 psid except as specified in (1) and.(2) below: (1) This differential shall be established within 24 hours of achieving operating temperature and. pressure. The differential pressure u may be reduced to less i than 1.1 psid 24 hours-s; prior to a scheduled shutdown. (2) This differential may be decreased to less than 1.1 psid for a maximum of four hours during required operability testing of the HpCI system, RCIC system and-the-drywell-pressure suppression chamber vacuum breakers. BFN 3.7/4.7-12 Unit 3 / c r. .s@ r.

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5-__

_____.m_.

= 3.'7/4.7' CONTAINMENT SYSTEMS - LIMITING-CONDITIONS FOR OPERATION -SURVEILLANCE. REQUIREMENTS 1 4.7.8. Standby Gas Treatment. '3.7.B.' Standby Gas - Treatment System : System 3.7.b (Cont'd).

b. If the differentia 1' pressure of Specification 3.7.A.6.a cannot be maintained and the differential pressure cannot be' restored within the subsequent six-hour period, an' orderly shutdown.shall be

-initiated and the reactor shall be in the Cold Shutdown-condition within 24' hours.

1. Except as specified in 1..At least once per. year, Specification-3.7.B.3 below, the following conditions-all three trains of the.

shall be demonstrated, standby gas treatment system shall be OPERABLE at all a. Pressure drop-across times when secondary the> combined HEPA containment' integrity is. filters andfcharcoal-adsorber banks is:less

required, than 6 inches-of water l

at a flow of 9000 cfm l (+ 10%). 1 b. The inlet heaters on each circuit are tested'in accordance with ANSI N510-1975, and areicapable of'an output of at-least '40 kW. c. Airfdistribution is ~ uniform within'20% across HEPA filters and charcoal adsorbers. 'c $[!t3 3*7*7-l' 4 'e o um_______

g -=_ - -- =,, 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE 1 REQUIREMENTS 3.7.C. Secondary Containment 4 If refueling zone secondary containment cannot be maintained-the followin'g conditions shall be met:

a. Handling of spent fuel and all-operations overfspent' fuel pools and open reactor wells containing fuel shall be prohibited.

b. The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure'the achieving of a vacuum of at least 1/4-inch of~ water and not over 3 inches of water in a11'three reactor i

zones. D Primary Containment Isolation Valves D. primary Containment Isolation Valves

1. During reactor power operation,

1. The primary containment all isolation valves listed in isolation valves Table J.7.A and all reactor surveillance'shall be coolant system instrument'line performed as follows:

flow check valves shall be q OPERABLE except as specified

a. At least once per

.i in 3.7.D.2. operating cycle, the OPERABLE isolation valves that are power operated and j automatically initiated shall-be^ tested foru j simulated automatic ) initiation.fand in-i accordance with Specification 1.0.MM, tested for closure times. l BFN Unit 3 3.7/4.7-17 i f ~' .j l

7 .o '3'7/4.7' CONTAINMENT SYSTEMS' LIMITING' CONDITIONS'FOR' OPERATION' SURVEILLANCE: REQUIREMENTS' 4.7.D.V i rimary Containment'- P '3.7kD. Primary-Containment Isolation Valves

Isolation-Valves 4. 7'. D.1 ! ( Con t ' d )

T l'

b. In ace'ordance'withi Specification /1.0.MM-iall 4

normally open power operated isolationLvalves: 'shal1~be' functionally; j r tested. X. fc. Attleast twice.per week, the main. steam line : power-operated isolation; 4. valves shall'-be' exercised' one.at.aitime by-partial closure'and. subsequent, reopening, d.'At least once.per' operating! cycle, the: operability of: the'reactoh coolantisystem instrument line flow cheet l valvesLshallLbe' verified.-

2. In the event any isolation valve.

2. Whenever;an;isolationLyalve specified in Table 3.7.A becomes listed in' Table'3.7.A'is'.

INOPERABLE, reactor power-INOPERABLE,sthe position offat l l operation may. continue provided least one'other valvetin each' at least one valve ~in each line line:havingLan INOPERABLEfvalve having an INOPERABLE valve is in shall: be recorded. daily' the mode corresponding to the isolated condition.

3. If Spec'ification 3'.7.D.1 and 3.7.D.2 cannot be met, an-orderly shutdown shall be initiated and the reactor shall be in the Cold' Shutdown condition-within 24 hours.

i 1 BFN Unit'3 3.7/4.7-18 . /. - - -.. - _ = _. -.-. _ _ _ _

o l: =m a-3 2 7h4.' 7 ' CONTAINMENT ~ SYSTEMS' ~ e j s L. LIMITING CONDITIONS FOR OPERATION: SURVEILLANCE REQUIREMENTS; 4.7.G. -Containment AtmosphAre .>L 73.7.G.- Containment Atmosphere' Dilution System (CAD).; ' Dilution-System (CAD)-

The Containment Atmosphere l '. ' System Operability:

~ 1. Dilution (CAD) System shall" be.0PERABLE with: y. .s-- -a. Two' independent .a.. Cycle'each solenoid l systems! capable of-

operated air / nitrogen =

L supplying nitrogen -valve through.Lat least- 'to.the drywell and1 one complete cycle of torus. full travel in'accordance-with Specification 1 y I'.0.MM, and:atfleast once d perfmonth verify'that- ] each manuale valve in the. '*] ' flow path:is open.c b. A minimum' supply ~of

b. :1 Verify;that the CAD:

j 2,500 gallons of ' System contains a:- 'y liguid nitrogen per minimum supply,of;. -2,500' gallons of liquid nitrogen.twice per week". l. system. i 2. The Containment Atmosphere. Dilution (CAD)l System'shall-be OPERABLE whenever the. ~ readtor mode. switch'is in-the."RUN" position. ]! 3. If one system is INOPERABLE,- j the' reactor may' remain in. l operation for a period of' 30 days'provided all active q components in the other l system are OPERABLE. ] 4. If Specifications 3.7.G.1 and 3.7.G.2, or 3.7.G.3. cannot be met,'an orderly shutdown shall be initiated and the reactor.shall be in the Cold Shutdown' condition, within 24 hours'. ~ 'l ~ 5. Primary containment' pressure-shall be limited'to a maximum of 30 psig during repressurization following a j loss of coolant accident. BFN i o Unit'3 3.7/4.7-22' f i i 3 2

_( lt - 3.7/4.7 ' BASES (Cont.d)> .3 Groups 4 and 5 - Process lines'are designed,to remain' operable and mitigate the consequences.of an accident which results in.the isolation of;other: process lines. 'The signals.which initiate. isolation'of, Groups-4'and.5Lprocesr; lines are therefore indicative of..a condition.which.would~ render them* inoperable. ' Group 6~- Lines are connected to the primary containment.but not directlyLto -the reactor vessel. These valves are isolated on reactor low water level (538") high drywell pressure, or reactor building ventilation high radiation. which would: indicate a possible ace dent and necessitate primary. containment _ 'i . isolation. Group 7 - Process lines are closed only on'the respective turbine steam supply valve not fully l closed. This ensures that the valves are not open when HPCIS l or RCICS action is required. J' Group'8 - Line (traveling in-core probe) is' isolated on high drywell pressure : ~ or reactor low water level'(538").- This-is to assure that'this line does'not provide a leakage path when containment pressure or-reactor water level l indicates a possible accident condition. The maximum closure time for the automatic' isolation. valves of the primary containment and reactor vessel isolation control system have been selected inL consideration of the design intent'to prevent core. uncovering-following pipe-breaks outside the primary containment'and the need to'contain released fission products following pipe breaks inside-the primary containment. In satisfying this design ~ intent an additional' margin has been included in ,specifying maximum closure times. 'This margin. permits identification of. degraded valve performance, prior to exceeding the design' closure times.. ~ In order to assure that the doses.that may result from'a steam line break do. not exceed the 10 CFR 100 guidelines,--it is-necessary that'no fuel' rod' perforation resulting from the accident occur prior to closure of the main .] steam line isolation valves. Analyses indicate that fuel rod cladding. perforations would be avoided for main steam valve. closure. times, including instrument delay, as long as 10.5 seconds. These valves are highly reliable, have low service requirements, and most are normally closed. The initiating sensors and associated trip, logic are also. checked to demonstrate the capability for automatic isolation..The test failureprobabilityof1.1x10ycleforautomaticinitiationresultsina interval of once per operating c that a line wil1~not.. isolate. More frequent testing for valve operability in accordance with Specification 1.0.MM' results in a greater assurance that'the valve will be operable when needed. The main steam line isolation valves are functionally tested per Specification 1.0.MM to establish a high degree of reliability. The primary containment is penetrated by several small diameter Instrument lines connected to the reactor coolant system. Each instrument line contains. a 0.25-inch restricting orifice inside the primary containment and an excess-flow check valve outside the primary containment. BFN f Unit 3 3.7/4.7-48 ~ - ~ - ~... -__._-_.____-A--___.-._.__._ .__.,-_-_-.La.---___.xa

1 ENCLOSURE ~2 1 DESCRIPTION AND' JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN) Description of Change d This change adds an ASME Section XI Pump and. Valve Program definitions (BFN TS 1.0,MM) and. changes monthly pump and motor operated valve (MOV) operability l requirements to reference this-definition. Once per cycle testing of check and: l relief valves, as well as the exercising of vacuum breakers and primary containment isolation valves, has also been changed to reference specification 1.0.MM.-'A. listing of the changes follows, and effective pages for this change'are listed in j. - 1 BFN ] 4 TS EXISTING BFN TS PROPOSED CHANGE 1.0.MM None Add new ASME Section XI- ' I Pump and Valve Program. definition. 4.3.F.1.b "The scram discharge volume "6 .~ demonstrated operable in ^ drain and vent valves shall accordance with specification be demonstrated operable-1.0.MM." monthly." 4.4.A.1 "At least once per month " Verify pump operability in each pump loop shall be accordance-with-specification functionally tested." 1~.0.MM." 4.5.A.1.b "Once/ month" "Per specification 1.0.MM" and 4.5.A.1.c 4.5.A.1.e "Once/ operating cycle" "Per specification 1.0.MM" l 1 4.5.B.1.b "Once/ mon th" "Per specification 1.0.MM" and 4.5.B.1.c 4.5.B.I.e "Once/ operating cycle" "Per specification 1.0.MM" 4

---

..--------.u-

---u-_. - - - --.n.-------a-----x---

't j ~ ..l BFN TS EXISTING BFN TS' PROPOSED CHANGE 4.5.B.9 "When the reactor vessel- . shall be' demonstrated to' pressure is atmospheric, .be OPERABLE,per specification j s d the RHR pumpsfand valves-1.0.MM." that are. required to be-l OPERABLE shall:be 1 demonstrated-operable L monthly. 3 4.5.C.1.a "Each of the RHRSW pumps- ... demonstrated OPERABLE in l l and all associated essential accordance with specification. control valves for-the EECW 1.0.MM." headers and RHR heat ex-changer. headers shall be-demonstrated to be OPERABLE'once every three months." 4.5.E.1.b "Once/ month"- "Per specification'1.0.MM": f and 4.5.E.1.c 4.5.F.1.b "Once/ month" "Per' specification 1.0.MM" j and 4.5.F.1.c 4.5 Bases "The pumps and motor operated "The pumps and. motor operated injection valves are also injection valves are also' tested tested each month..." in accordance with specification d 1.0.MM. "A simulated automatic '"A simulated automatic actuation test once each actuation test once each. cycle cycle combined with monthly combined with testing of pump tests of pump and injection and injection. valves in-l valves..." accordance~with' j l specification 1.0.MM, 4.6.D.2 "Once during each operating "In accordance with cycle..." specification-1.0.MM. 1 3.6.D/4.6.D "The relief valves are tested "The relief valves are. tested in BASES in place once per operating place in accordance with' cycle..." - specification' 1.0.MM. -. ;."- 4.7.A.3.a ... vacuum breakers shall ... vacuum breakers shall be be exercised and the exercised in accordance with associated instrumentation..." ' specification 1.0.MM, and. the the associated' instrumentation..." s ~ m__.__________________________________

i BFN ,t TS EXISTING BFN TS l PROPOSED CHANGE { 4.7.A.4.a . shall be exercised. .lshall be tested in= through an opening-closing accordance withLspecification .i cycle every; month." - 1.0.MM."- 4.7.A.4.c "Once each operating cycle each "Each vacuum breaker' valve shall: 1 vacuum breaker valve shall be. be. inspected for proper operation inspected for proper operation of the valve'.and'11miteswitches-of the valve and limit switches." in accordancelwith specification i 1.0.MM."- -l 4.7.D.I.a "At least.once per operating '"At least once per operating- .cyc1','the OPERABLEfisolation cycle, the OPERABLE isolation e valves that are power' operated valves that are powerfoperated and' automatically initiated and automatically linitiatedl shall be tested for simulated shall be tested for simulated automatic initiation and automatic initiation and, in' closure times." accordance with specification 1.0.MM, tested for closure ' times." i 4.7.D.1.b "At least once per. quarter: "In accordance with specifi-cation 1.0.MM, all.normally open (1) All normally open power. power operated isolation valves operated isolation valves shall'be functionally' tested." (except for the main steam line power-operated isolation valves) shall'be fully closed and reopened."- (2) "with reactor power less Delete than 75% trip main steam isolation valves' i individua11y'and verify closure time." 4.7.G.1.a "At least once per month cycle " Cycle each solenoid operated ~ each solenoid operated air / air / nitrogen valve through at nitrogen valve through at least one complete cycle of full least one complete cycle of travel in accordance with full travel and verify that specification 1.0.MM, and at each manual valve in the flow least once perfmonth verify that path is open." each manual valve in the flow. path is open;" t l oh k L_..___________. __l_._

WQ

N

= p,,. 1 '5 ,k, }j, j 1 suy c .r p i 3 J '{ 1 .t BFN ~ TS. ' EMSTING-BFN TS -PROPOSED CHANGE. ( I { 'L 3.7.D/4.7.D; "More frequent.testinr,'for- "..:. valve.operabilityffna BASES ' valve operability results.in. accordance with spedfications a greater assurance'.that the' 1 0'.MM results'in. % :"!

valve will be operable when t

/r mj y l .needed." ,,c' + "Themainsteam?1ineihola, "Themainsteamiline?idolatjon i r L valves:are functionally; tested tion valves'are functio'nally ' per specification 1.0.MMLto tetted on a. :nore frequent. interval to establish:a high establishLa highedegree of-degree'of reliability.% ~ reli abili ty. 'E rf -Reason for Change g The changes outlined and listed above are being made to refle m.ih.a ASME Section XI Pump and Valve Program for Browns-Ferry Units"1,'2,1and 3"~hich was submitted w to NRC on 12/23/86. Testing in accordance with Section XI of:tho'ASME Boiler and Pressure Vessel Code is required by.10 CFR:50.55a(s).-- au ]~ Y Justification of Change 4, dic 3 Testing in accordance with ASME Section XI-is required by 10. CFR 50.55a(s)'. By, adding an ASME section XI pump andivk3vs program definition:to BFN Technical-Specifications (TS) and referencingNthi s definition. throughoucl applicable pump and valve TS surveillance requirements, consistency between TS.and the ASME:. Section II pump and valve program can bermore readily maintained fAs changes-are made to the program and/or the ASME code; the necessity for future TS. amendments to maintain this consistency will be reduced.. The substantive' changes of this' request involve the frequency of testing ASME Section II pumps. motor operated valves.g, solenoid operated air / nitrogen valves, 'd, the closure time testirG cf main steam' Isolation valves.'(MSIV),. the exercising of vacuum breakers, and. operability testing o't.the scram'ditchtege volume drain V and vent valves. These componente,are' currently tested monti 4 vithithe exception of MSIV closure time testing which is quarterly. 1 Earlier editions,of~ j l the ASME code required monthly opkability testing of'some'of these components. i I However, later editions-(beginning %ith 1979' edition / Winter 1979 addenda)- changed monthly frequency requirements to quarterly. The code change was made because monthly testing caused' unnecessary wear to. safety related, components, and increased the probability of system misalignments.resulting:from. returning' Y the systems to their normal configurations following testing.scTestingiin- -11 accordance with ASME Section:XI results in-use of a'more optimum test R [t frequency. The current! ASME code of record for.BFN ic the 1980' edition / Winter - j i; 1980 addenda. Clanging.tthe TS frequency requirements to reference-the ASME q Section II pump and valve: testing program does not affect the intent-of:the TS <j which is to perform pump!and valve operability testing in accordance with.the: j 1/s 1 requirements of 10 CFR 50.55a. l n .l 1 (. .1 q j .b j, t

- m3, 1 o . 'l !j Justification of Change (Cont'd) 1 l Operability testing frequencies for other components. tested under the ASME ) Section XI pump and valve program are not effectively changed by this j j 1 amendment. The frequencies are only changed to reference the pump and valve program which requires testing at the intervals currently specified in BfN TS. l The proposed amendment does not change the amount of plant equipment tested, the acceptance criteria, or the me'thod of testing. The changes proposed by this amendment to BFN TS are similar to those found in recently issued TS for Hope Creek Generating Station (NUREG 1202) and Limerick Generating Station (NUREG 1088). For the reasons stated above, these changes will not adversely effect the margin of nuclear safety. l ../ 1 l l l a, e ') 4 ,b t .f ' ) ,..i s

(+ 1 J 1 /r j u. / . j d j j j t / ENCLOSURE 3 / DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION l r4 l Description D o Significant Hazards Consideration i I The proposec amendment would m d!,fy the Browns F$rry Nuclear Plant Technical l Specification'is for units 1, 2 ce % 3 to refernge the ASME Section XI Pump and 2 Valve 'Progrw\\ definition (1.bf"M) for applicabl4 pump and valve ter. ting / frequencies. I' /\\ \\ \\ Basic for Propo3od No Significant Hazards Consideration Determination i i s Th4 Comniission has providec/att.ndards for determining whether a signi.ficant he.zards consideration exists as stated in 10 CFR 50.92(c). A pro' posed amendment to an operating license involvos~ne significant hazards considerations if operation of the facility in accordance with the proposed amendment:would not (1) involve a significant inerence in the probability or consequence of an accident previously evaluated, or (2) create the possibility of a new! 0r different kind of accident from an accident previously evaluated, or v3h involve a a significant reduction in a fart (iv,of safety. A discussion of these standards as they relate to the proposed amendment. follows. 1. This amendment provides for consistency between the ASME Section XI pfmp and / valve program for BFN and_BFN Tech'nical Specifications (TS). Existing monthly pump and valve TS surveillance requirements comply with the intent of early editions of the ASME code which required once per month operability testing of some components. The ASME code of record referenced in the recently submitted revised BFN pump and valve program specifies an edition of the code which roquires these components to be tested quarterly. The code was changed beca'uso monthly testing was determined to be excessive, potentially causing unnecessary wear to pumps and valves. Referencing the ASME Section XI program will effectively irnprove yt;e reliability of these ecmponents by the use of a more optimum testing frequency. Therefore, the intent of BFN TS is not affected by amending these opet' ability surveillance requirements to use a more optimum testing frequency. ~ ) Operability testing for valves whir.h are tested at frequencies other than monthly and tested per ASME Section XI are not effectively changed by this amendment. They are on:y changed to reference the ASME Section II pump and valve program which requires testing at the intervals srscified currently in BFN,TS. The changes made by this amendment do not alter the intent of any TS. Therefore, thaiprobability of any previously evaluated accideat will remain unchanged or slightly decreased,'and the consequences of such accidents will not be affected F t z

E I

{

e'- .k i

• t

[ -

Basis'for Proposed No S r,nificant Hazards Consideration Determination The existing testif'requencies for applicable pumps and valves arell'ntendede 2.

-to. meet.10 CFR 50.55a requirements..The: changes..being'made bylthis' amendment do.n'ot' alter theLintent ofz BFN.TS.3 The: amendment will notichange' the' method'of. testing.ori he~ current: acceptance criteria;forfthe applicable. ~ t ~ Lequipment;.No' method or!11m ts'o; f' operation are'beinglehanged..therefore,' i no.new accident" possibilities are created. Theoriginal/intentof/theTS'hasnotbeen.affectedibyfthesechanges'.fsihce 3. operability testing.will. still' be performed but' at 'an. improved < frequency.. ~ Testing in accordance with the ASME code edition referenced;in the recently-submittedL pump and' valve Program.for.BFNl will result in; a more, optimum testing

• frequency /for certain-pumpsiand. valves because the existing. monthly.

1 frequency requirements-cause' unnecessary wear:to pumpLand. valve components.: .Therefore,,the margin of safety.has not been-reduced..and could be slightly: ' increased. Since~the application for amendment ~invdives proposed changes.thatuare, encompassed'by the criteria for.which no significant: hazards consideration exists,-TVA:has made a proposed' determination ~.that the application involves;noj significant hazards consideration. j e 1 1 I s' l ( w gg<

N c,,-7 - 1 ENCLOSURE 4-BROWNS FERRY / NUCLEAR PLANT TECHNICALLSPECIFICATION CHANGEJ . EFFECTED PAGE LIST. UNIT l' h '2.0 12,:13 3.3/4.3 -.11 3.4/4.4 - 1 3.5/4.5-1,2;4,7,9(13,f 14,' 35-3.6/4.6 - 10,'30 ~

3. 7 / 4. 7 -.10, 11~, ' 12, 13,~ 17. 18, 2 2 ', 50 -

UNIT 2 1.0 - 11,-12 3.3/4.3 11 3.4/4.4 - 1 j 3.5/4.5 - 1, 2,.4 7, 9.-13,:14, 33' .3.6/4.6 - 10, 30 3.7/4.7 - 10, 11, 12,:13, 17,'18, 22, 50 UNIT 3 1.0' - 12, 13' 3.3/4.3 - Il 3.4/4.4'12 3.5/4.5 - 1, 2, 4, 7, 9,,13, 14, 36 l 1 3.6/4.6 - 10, 30 3.7/4.7 - 10,.11, 12, 13,;17, 18, 22, 48 1 l j l r i d - g 1 l 9 k ..- >}}