ML20210L438

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Proposed Tech Specs Revised Typed Pages for TS Change Requests 213 & 80,requiring Addl Revs from Pages Submitted in
ML20210L438
Person / Time
Site: Beaver Valley
Issue date: 08/13/1997
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20210L434 List:
References
NUDOCS 9708210150
Download: ML20210L438 (55)
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{{#Wiki_filter:k. . t.- i ? ATTACHMENT A-1 i. Unit No.1 Marked Up Technical Specification Pages I j-( d i T i i i 1

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- 9708210150 970813 PDR ADOCK 05000334 p PDR

I t DPR-66 PLANT SYSTJ;MS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION ) Three Auxiliary gedwater (AFW) trains shall be OPERABLE and 3.7.1.2 -con 31st of the followings One motor driven AFW pump with a flow path from WT-TK-10 to a. each feedwater injection header via the train "A" supply header. i b. One motor driven AFW pump with a flow path from WT-TK-10 to each feedwater injection header via the train "B" supply header. g c. One turbine driven AFW pump capable of being powered from two steam supplies with a flow path from WT-TK-10 to each feedwater injection header via the designated train supply header. d. One feedwater injection header to each steam generator. APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator (s) is relied upon for heat removal. ACTION: With one of the two steam supplies to the turbine driven AFW a. i pump inoperable, restore two steam supplies to OPERABLE status within 7 days and within 10 days from discovery of failure to meet the LCO or be in HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours, b. With one feedwater injection header inoperable in MODE 1, 2, or 3, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. (1) Only one AFW train (capable of providing flow to the steam generator (s) relied upon for heat removal), which includes a motor driven pump, is required to be OPERABLE in MODE 4. ( Wikh ems skesm supp mopeeoMe. [*NCW ' MTION 3 4* k A00 BEAVER VALLEY - UNIT 1 3/4 7-5 Amendment No. hropo5ec\\ Worb m

DPR-66 , PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) With one AFW train inoperable in MODE 1, 2, or 3 for reasons c. other than one of the two steam supplies or one feedwater injection header inoperable, realign the two AFW pumps to separate train supply headers within 2 hours if both train supply headers are operable, and restore the AFW train to OPERABLE status within 72 hours and within 10 days from discovery of failure to meet the LCO or be in HOT STANDBY within the 6 hours and in HOT SHUTDOWN within the following6gext hours. d. With two AFW trains inoperable in MODE 1, 2, or 3 fee 6:55: Other nsN ene of t"- 590 ertu s'2rrliee increrrbly, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. DELETE e. With thres__AFW trains inoperable in MODE 1, 2,i.:;tr[3 or _ 4.e g r e e_M c**-- ** " err er *Ne tee ster c'2pplic: ib h, immediately init action to restore one AFW train to OPERABLE status. gte f. With the required AFW train inoperable in MODE 4, immediately initiate action to restore one AFW train to OPERABLE status. l l SURVEILLANCE REQUIREMENTS - - - - - - - - - - - - - - GENERAL NOTE - - - - - - - - - - - - - - Establish. and maintain constant communications between the control room and the auxiliary feed pump room while any normal AFW pump discharge valve is closed during surveillance testing. I l I (2) This time period may be extended for up to 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. (3) LCO 3.0.3 and all other LCO ACTION statements requiring MODE changes are suspended until one AFW train is restored to OPERABLE status. BEAVER VALLEY - UNIT 1 3/4 7-6 Amendment No. hcopo3th Of $^

DPR,66 PLANT SYSTEMS SURVEILL*WCE REQUIREMENTS (Continued) 4.7.1.2.1 Verify each AFW manual, power operated, and -automatic valve in each wkter flow path, and in both steam supply flow paths to the steam turbine driven AFW pump, that is not locked, sealed, or otherwise secured in positi in the correct position at least once per 31 days. g, is 4.7.1.2.2 Verify operability of each River Water Auxiliary Supply valve by cycling each manual River Water to Auxiliary Feedwater System valve through one complete cycle at least once per 31 daysi. 4.7.1.2.3

Verify, at the frequency specified in the Inservice Testing-Program, on a STAGGERED TEST BASIS that the developed head of each AFW pump at - the flow test point

~ is greater than or equal to the required developed head as specified in the Inservice Testing Program. The provisions of Specification 4.0.4 are not applicable for entry i 3 for the steam turbine driven. pump testing. g MODE 4.7.1.2.4 Verify each AFW automatic valve that is not locked, sealed, _ or otherwise secured "in position,- actuates to the correct position on an' actual og simulated actuation-signal at least once per 18 months 4.7.1.2.5 Verify.each AFW pump starts automatically on an actual or sin actuation signal -at least once per - 18 months.g g d 4.7.1.2.6 Cycle each power operated.(excluding automatic) valve in the flow path that is not testable during plant operation, through at least one complete-cycle at leact once per 18-ronths during shutdown. 4.7.1.2.7 Verify AFW flow from - WT-TK-10 to-the Steam Generators-with the AFW valves in their normal alignment. W -- ( 4 ) Reverify these requirements by a second and independent operator. (5) Not required to be performed for the turbine driven AFW pump until 24 hours after establishing the minimum required secondary side staan_ pressure of greater than 600 psig. (6) Not applicable in MODE 4hhon Mesmy**d*ID) ti It.ht M tswoou (7) This surveillance is required to be performed prior to entry into MODE 2-whenever the plant has been in MODES 5 or 6 for greater than 30 continuous days. BEAVER VALLEY - UNIT 1 3/4 7-6a Amendment No.

DPR-46 ~ . PLANT SYSTEMS BASES 2f4.7.1.2 ' AUXILIARY'FEEDWATER SYSTEM (AFW) LCO (Continued) for all events accompanied by a loss of offsite power and a single failure.- This - is accomplished by powering two of the pumps from independent emergency buses. - The - third AFW pump is powered by a =different - means, a steam driven turbine supplied with steam from a source that is not - isolated by closure of the main steam isolation valves (MSIVs). The'AFW System is configured into three trains. The AFW System is considered OPERABLE when the components and flow paths required to provide redundant AFW flow to the steam generators are OPERABLE.- This requires that the two motor driven AFW pumps be OPERABLE in two diverse paths, each supplying AFW to each steam generator. The turbine driven AFW pump is required to be OPERABLE with redundant steam supplies from two of the-three main steam lines upstream of the MSIVs,'and shall be capable of supplying AFW to the steam generators via the designated train supply header. The

piping, valves, i

instrumentation, and controls in the required -flow paths also are required to be OPERABLE. g l The LCO is modified by a-mete + Note (1) indicates that one AFW train l (capable of providing flow to the steam generator (s) relied upon for-heat removal), which includes a motor driven pump, is required to be OPERABLE in-MODE 4. This-is because of the reduced heat removal requirements and short period of time in MODE 4 during which the AFW may : be required and the insufficient steam available in MODE 4-to power the turbine driven AFW pump.%00 TNSEAT,C" AP_P_LICABIL1 "X In MODES 1, 2, and 3, the AFW System is required to be OPERABLE in the event that it is called upon to function when the MFW is lost. In addition, the AFW System is required to supply enough makeup water to_ replace the steam generator secondary inventory lost as the unit cools to MODE 4 conditions. In MODE :4, the AFW System may be used for heat removal via the steam generators. In MODE 5 or 6, the steam generators are not normally used for heat removal, and the AFW System is not required. BEAVER VALLEY - UNIT 1 B 3/4 7-2c Amendment No.. (fropeac) Mo

Attachment to Auxiliary Feedwater Systeni ' INS ERT "C" - Note (8) states that with one steam supply inoperable, follow ACTION statement a. This condition does not constitute one AFW train being inoperable. The train associated with the turbine driven AFW pump continues to be capable of perfonning its intended function assuming no failure of the remaining OPERABLE steam supply, BEAVER VALLEY - UNIT 1 (Proposed Wording)

-DPRL66-- N

  • PLANT SYSTEMS Ths Q,bn doe,$ wsk cowsh.h\\t, ovw_-

Fuj krom h 4%ef>a.c=M t, j BASES-3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) (Continued) ACTIOhS a. If 'one of the two att am supplies. to the turbine driven AFW train is inoperable, action must be taken to restore OPERABLE status withir 7 days. The 7 day completion time is reasonable, based on the following reasons: 1. The redundant OPERABLE steam supply to the turbine driven AFW pump; J 2. The availability of-redundant OPERABLE notor driven AFW-pumps; and l 3. The low probability of an event occurring that requires l the inoperable steam supply to the turbine driven AFW pump. The second completion time for ACTION statement a establishes a limit on the maximum time allowed for any combination of conditions to be inoperable during any continuous failure to meet this LCO. The 10 day completion time provides a limitation time allowed in this.specified condition after discovery of failure to meet-the LCO. This limit is considered reasonable--for situations in which ACTION statements a and c -{g are entered concurrently.- The &HQ connector between 7 days f a et and 10 days dictates that both completion times apply-gNsfWT A simultaneously, and the more restrictive must be met. b. With one feedwater injection header inoperable-in MODES-1, 2, or 3, the unit must be-placed in a MODE in which the-LCO does not apply. To achieve this status, the unit must be . placed in at least MODE 3 within 6 hours, and -in MODE 4 within the following 6 hours. The allowed completion. times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and:without challenging unit systems. In MC 'E 4 with one feedwater injection header inoperable, operation is allowed to continue because only two steam generators are required.to remove decay heat per LCO 3.4.1.3, "RCO-SHUTDOWN."h- --\\hho p ne p re p ice) A t u w,4 vgo y on6we. h. ciel die ad *w A tah. Rd.; BEAVER VALLEY - UNIT 1 B 3/4 7-2d Amendment No. (frofsse b '^

L Attacliment to Auxiliary Feedwater System INSERT "A" If the inoperable steam supply cannot be restored to OPERABLE status within the required -(completion time, the plant must be placed in a MODE in which the LCO does not apply. To achieve this status, the plant must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without-challenging unit systems. In MODE 4 with one steam supply inoperable, operation is allowed to continue because only one AFW train, which includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO, Although not required, the unit may continue to cool down and initiate RHR. BEAVER VALLEY - UNIT 1 (Proposed Wording)

  • DPR-66 PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW)

ACTIONS (Continued) c. With one of the required AFW trains (pump or flow path) inoperable.in MODE 1, 2, or 3 for reasons other than ACTION statements a or b, action must be taken to restore OPERABLE status within 72 hours. This condition includes the loss of two steam supply lines to the turbine driven AFW pump. The 72 hour completion time is reasonable, based on redundant capabilities afforded by the AFW System, time needed for repairs, and the low probability of a DBA occurring during this time period. The second completion time for ACTION statement c establishes a limit on the maximum time allowed for any combination of conditions to be inoperable during any continuous failure to meet this LCO. l The 10 day completion time provides a limitation time allowed in this specified condition after discovery of failure to meet the LCO. This limit is considered reasonable for situations in which ACTION statements a and c are entered concurrently. The MQ connector between 72 A D O,,, hours and 10 days dictates that both completion times apply gg Q simultaneously, and the more restrictive must be met. L ACTION statement c is modified by a note. Note (2) states that the completion time of 6 hours to reach HOT SHUTDOWN may be extended for an additional 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. This extension of the required completion time to reach MODE 4 from MODE 3 to 96

hours, allows additional time to complete any necessary repairs and/or testing of the turbine driven AFW pump prior to initiating a plant cooldown to MODE 4.

d. When two AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experjence, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. BEAVER VALLEY - UNIT 1 B 3/4 7-2e Amendment No. ($rofshc.c\\ U O

Attacl$ ment to Auxiliary Feedwater System INSERT "B" If the inoperable--AFW train cannot be restored to OPERABLE status within the required completion thne, the plant must be placed in a MODE in which the LCO does not apply. To - achieve this status, the plant must be placed in at least MODE 3 within 61 Surs, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with one AFW train inoperable, operation is allowed to continue because only one AF_W train, which includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR. BEAVER VALLEY - UNIT 1 (Proposed Wording) __ _J

  • DPR-66 PLANT SYSTEMS BASES 3/4.7.1.2 -AUXILIARY-FEEDWATER SYSTEM fAFW)

ACTIONS (Continued) PD(,L% r M In MODE ' 4 with two AFW trains inoperable,iroperation is g NmtNC -jw allowed to continue because-only one C=t:r Oriv_.. wu-J AFW a N\\W km traina is required in accordance witt the Note (1) that modifies -the LCO. Although not - required, the unit may 8"/) continue to cool down and initiate RHR. e. If all three AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the -feedwater injection headers, the unit is-in a seriously degraded condition with no safety-related means for conducting a cooldown, and only limited means for conducting; a cooldown with nonsafety related equipment. In such a condition, the unit should not be perturbed by any action, including a power change, that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status. ACTION statement e is modified by a Note (3) indicating that all required MODE changes or power reductions are suspended until one AFW train is restored to OPERABLE status. In this case, LCO 3.0.3 is not applicable because it could force the unit into a less safe condition. h MODEM) f. WithonerequiredAFWtraininoperablefactionmustbetaken to immediately restore the inoperable train to OPERABLE status. The immediate completion time is appropriate due to the need to ensure that a safety related means of providing flow to the steau generator (s), for the purpose of core decay heat removal, is available. SURVEILLANCE REQUIREMENTS (SR) The Surveillance Requirements are -modified by a General Note which requires = that constant communications be. established and maintained when any normal AFW pump discharge valve is closed during . surveillance-testing. SR 4.7.1.2.'1 Verifying the correct alignment for manual, power operated, and automatic valves in the AFW System water and steam supply flow paths provides assurance that the proper flow paths will exist -for AFW BEAVER VALLEY - UNIT 1 B 3/4 7-2f-Amendment No. (,frop o$ e.ck W O f j

~ DPR*66' . PLANT SYSTEMS BASES I m -3/4.7.1.2-AUXILIARY-FEEDWATER SYSTEM =(AFW) SURVEIT.TANCE REOUIREMENTS (SR) (Continued) - This SR is - modified by _ a Note (5) indicating that the SR should be deferred. until suitable test conditions are established for testing the turbine driven AFW pump. This deferral is-required because there is insufficient steam pressure to perform the test. SR 4.7.1.2.4 This'SR verifies that AFW can be delivkred to the appropriate steam generator in the event'of any accident or transient that generates an ESFAS, by - demonstrating-that each automatic valve in the flow-path actuates to its correct position on the actual or simulated actuation signal. The 18 month Frequency is-based on the need to perform this surveillance under the conditions that apply during a unit outage and t l the potential for an unplanned transient if the surveillance were i performed with thn reactor at power. The 18 - month Frequency is acceptable based on operating experience and the design reliability-of the' equipment. This'SR is modified by a Note (6) that states the SR;is not required I in MODE' providing% In MODE'4, the heat removal requirements would be less more -time for operator action : to. manually align the flow n 54eam M M 13 ft N Tenforhebfekedo SR 4.7.1.2.5 This - SR verifies that the AFW pumps will start in-the event of any accident or transient that generates an ESFAS by demonstrating that each AFW pump starts automatically _on.an actual or simulated actuation = signal. The 18 month-- Frequency is-based; on the - need to perform this surveillance. under the conditions that apply during a -unit outage Land the potential for an _ unplanned transient if the surveillance were performed with the reactor at power.- This SR is modified by_two notes. Note-(5) indicates that the SR be deferred -until suitable test conditions are -established for testing the= turbine driven AFW pump. _This deferral is required because there is. insufficient steam pressure'to perform the. test. Note (6) states that the SR.is not required in MODE-h In MODE 4, the heat _ removal requirements woula De less providing more time for-operator action to manually start the required AFW' pump. BEAVER VALLEY - UNIT 1 B 3/4 7-2h Amendment No.. ( heo pejed M C

4 ATTACIIMENT A-2 i Unit No. 2 Marked Up Technical Specification Pages

L. N P F.7 3 r . PLANT SYSTEMS AUXILIARY FEEDWATER SISTEM LIMITING CONDITION:FOR' OPERATION- ~ 3.7.1.2-Three Auxiliary _F and consist of the following ydwater (AFW). trains stall -be OPERABLE a. One motor driven AFW - pump with a flow path from TK-210 to each feedwater injection header via the train "A" supply header. b. One motor driven AFW pump with a flow path from TK-210 to - each feedwater injection header via. the train ~ "B" supply header.- g c. One' turbine driven AFW pump capable of being powered. from two - steam supplies with a. flow path from TK-210 to-each l feedwater injection header via the designated train supply I

header, d.

One'feedwater injection-header to each steam generator.- APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator (s) is relied upon for heat removal. ACTION: With one of the two-steam supplies to the turbine driven AFW a. pump inoperable,- restore-two steam supplies to OPERABLE status within -7 days -- and within 10 days from discovery of failure to meet the-LCO or be in HOT STANDBY within the next 61 hours and in HOT-SHUTDOWN within the following 6 hours. .b. With one feedwater injection header inoperable-in MODE 1, 2, or 3, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. (1); only 'one AFW train -(capable of providing-flow to the steam generator (s) relied upon for heat removal), which includes a motor' driven pump, is required to be OPERABLE in MODE 4. hhh one.-5ke.em Supp\\y mofeWo. j foMo w ACTjoQ s\\ h M q, Anol BEAVER-VALLEY - UNIT 2 3/4 7-4 Amanda,?nt No. ([topesch WC J

NPF,73 . PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) With one AFW train inoperable in MODE 1, 2, or 3 for reasons c. other than one of the two steam supplies or one feedwater injection header inoperable, realign the two AFW pumps to separate train supply headers within 2 hours if both train supply headers are operable, and restore the AFW train to OPERABLE status within 72 hours and within 10 days from discovery of f ailure to meet the LCO or be in HOT STANDBY within the 6 hours and in HOT SHU'lDOWN within the following6gext hours. i r. : r [: M e ', d. jfith two AFW trains inoperable in MODE 1, 2, or 4er ysesrene ether thi crr -" -- tv =t::: :::;110: 'ba in HOT STANDBY within 6 hours and ..n HOT SHUTDOWN within the following 6 hours. N e. ith three AFW trains inoperable in MODE 1, 2,_or

rger: etter d r ~550 ^* the "O currlic: incr:rrbl,

immediately init action to restore one AFW train to OPERABLE status, gte f. With the required AFW train inoperable in MODE 4, immediately initiate action to restore one AFW train to OPERABLE status. I SURVEILLANCE REQUIREMENTS - - - - - - - - - - - - - - GENERAL NOTE - - - - - - - - - - - - - - Establish and maintain constant communicat.4 ons between the control room and the auxiliary feed pump room while any norma) AFW pump discharge valve is closed during surveillance testing. 4 (2) This time period may be extended for up to 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. (3) LCO 3.0.3 and all other LCO ACTION statements requiring MODE changes are suspended until one AFW train is restored to OPERABLE status. l BLAVER VALLEY - UNIT 2 3/4 7-5 Amendment No. (hropo$ceb O M l 1

NPF-73 PLANT,1XSTEMS SURVEILLANCE REQUIREMENTS (Cor.tinued) 4.7.1.2.1 Verify each AFW manual, power o p e r a t e d,- a n d automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven AFW pump, that is not locked, sealed, or otherwise secured in posit inthecorrectpositionatleastonceper31 days.g,is 4.7.1.2.2 Verify operability of each Service Water Auxiliary supply valve by cycling each manual service Water to Auxiliary Feedwater Systen valve through one complete cycle-at least once per 31 days. 4.7.1.2.3

Verity, at the > frequency specified in the Inservice Testing Program, on e STAGGERED - TEST BASIS that the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head as specified in the Inservice Testing Program.-

The provisions of specification-4.0.4 are=not applicable for entry i 3 for the steam turbine driven pump-testing. g MODE 4.7.1.2.4 Verify each AFW automatic valve that is not

locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal at least once per is months.,3 4.7.1.2.5 Verify each AFW pump starts automatically on an actual or simulat months. g g etuation signal at least once per is 4.7.1.2.6 Cycle each power operatedis (excluding automatic) valve in the flow path that not testabla during plant operation, through at least one complace cycle at least once per is months during shutdown.

Verify AFW flow'from TK-210 to the Steam gnerators with 4.7.1.2.7 the AFW valves in their normal alignment.( Reverify these requirements by a second and independent -(4) operator. (5) Not required to be perfcrmed for the-turbine driven AFW pump until 24 hours after establishing the minimum required secondary side steam pressure of greater than 600-psig. -(6)- Not applicable in MODE 4 hem d ee m,y m ar*\\c d i P 1 eA renconhj (7) This surveillance is required to be performed prior to entry into NODE 2 whenever the plant has been in MODES 5 or 6 for -greater than 30 continuous days. BEAVER VALLEY - UNIT 2 3/4_ 7-5a Amendment No. (fropsStb Y' = =

0 NPFs73 . PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY PEEDWATER SYSTEM (AFW) j LCO (Continued) requires that the two motor driven AFW pumps be OPERABLE in two diverse paths, each supplying AFW to each steam generator. The turbine driven ATW pump is required to be OPERABLE with redundant steam supplies from at least two of the three main steam lines upstream of the MSIVs, and shall be capable of supplying AFH to the l steam generators via the designated train supply header. The piping, i valves, instrumentation, and controls in the required flow paths also are required to be OPERABLE. ggg] The LCO is modified by a n:tc. Note (1) indicates that one AFW train (capable of providing flow to the steam generator (s) relied upon for heat removal), which includes a motor driven pump, is required to be l OPERABLE in MODE 4. This is because of the reduced heat removal l requirements and short period of time in MODE 4 during which the AFW may be required and the insufficient steam available in MODE 4 to power the turbine driven AFW pump. A 00 TNSEftT,,F j g APPLICABILITY In MODES 1, 2, and 3, the AFW System is required to be OPERABLE in the event that it is called upon to function when the MFW is lost. In addition, the AFW System in required to supply enough makeup water to replace the steam generator secondary inventory lost as the unit cools to MODE 4 conditions. In MODE 4, the AFW System may be used for heat removal via the steam generators. In MODE 5 or 6, the steam generators are not normally used for heat removal, and the AFW System is not required. ACTIONS a. If one of the two steam supplies to the turbine driven AFW train is inoperable, action must be taken to restore OPERABLE status within 7 days. The 7 day completion time is reasonable, based on the following reasons: 1. The redundant OPERABLE steam supply to the turbine driven AFW pump; 2. The availability of redundant OPERABLE motor driven AFW pumps; and BEAVER VALLEY - UNIT 2 B 3/4 7-2c Amendment No. (ftsgend Wof

O Attachment to Auxiliary Feedwater System llNSERT "F" f l Note (8) states that with one steam supply inoperable, follow ACTION statement a. This condition does not constitute one AFW train being inoperable. The train associated with the l turbine driven AFW pump continues to be capable of perfonning its intended function assuming no failure of the remaining OPERABLE steam supply. l BEAVER VALLEY - UNIT 2 (Proposed Wording)

e, 3Ce nh ee! C6M$kiku\\t. 064. SYSTEMS AvwA6,g.a. J mAsEs }f4.7.1.2 AUXILIARY FEEDWATER SYSTEM fAFW) ACTIONS fContinued) 3. The low probability of an event occurring that requires the inoperable steau supply to the turbine driven AFW Pump. The second completion time for ACTION statement a establishes a limit on the maximum time allowed for any-- combination of conditions to be inoperable during any continuous failure to meet this LCO. The 10 day completion time provides a limitation time I allowed in this specified condition after discovery of-failure to meet the LCo. This limit is considered l l _ reasonable for situations in which ACTION statements a and c I ggy are entered concurrently. The Atm connector between 7 days 1 8 11 and 1 days di tatte that b th C apleti n times apply H3EfI 0jginultaneously, and the more restrictive must be met. b. With one feedwater injection header inoperable in MODES 1, 2, or 3, the unit must be placed in a MODE in which the LCo does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times. are rehsonable, based on operating experience, to reach'the required unit conditions fron-full power conditions in-an orderly manner and-.without challenging unit systems. In MODE 4 with one feedwater injection header inoperable, operation is allowed to continue because only two - steam generators are required to remove decay heat per LCO 3.4.1.3, "RCS-SHUTDOWN."j c. With _one of the required AFW trains (pump or flow path) inoperable-in MODE 1, 2, or 3 fcr reasons other than ACTION statements afor b, action must be taken to restore OPERABLE status within 72 hours.- This condition includes the loss of two' steam supply' lines to the turbine driven'AFW pump. The 72 hour completion time is reasonable, based on redundant capabilities afforded by the AFW.Systeta, time needed for repairs, _ and - the low probability of a-DBA occurring during this time period. /kMbup nd fs d; M M'

    • ) Cs tut. d e com) y oO W.&% W.

A =' BEAVER VALLEY - UNIT 2 B 3/4 7-2d Amendment No. (fropt.3ed Wetdi

0 Attachment to Auxiliary Feedwater S McDn o Y lNSERT "D" If the inoperable steam supply cannot be restorei to OPERABLE status within the required completion time, the plant must be placed in a MODE in which the LCO does not apply. To achieve this status, the plant miist be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. I In MODE 4 with one steam supply inoperable, operation is t.llowed to continue because only one AFW train, which includes a motor driven pump, is required in accordance with Note (1) l that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR. l l t BEAVER VALLEY - UNIT 2 (Proposed Wording) t

NPF-73: ' PLANT SYSTEMS

  • BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW)

ACTIONS (ContinuggQ The second completion time for ACTION statr, ment c establishes a limit on the-maximum time alloired for any combination of conditions to.be inoperable during any continuous failure to meet this LCO. The 10 day completion time provides a limitation time allowed in this specified condition after discovery of failure-to meet the LCO. This limit is considered l reasonable for situations in which ACTION statements a and c ~ are entered concurrently. The AHQ connector between 72 b 3 hours ~and 10 days dictates that both completion times apply er H simultaneously,-and the more restrictive must be met. ' TN568I W k ACTION statement c is modified by a note. Note (2) states that the completion time of 6 hours to reach HOT SHUTDOWN may be extended for an additional 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. This extension of the required completion time to reach MODE 4 from MODE 3 to 96

hours, allows additional time to complete any necessary repairs and/or testing of the turbine driven AFW pump prior to initiating a plant cooldown to MODE 4.

d. When two AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. gg yg: In MODE 4 with two AFW trains inoperable, aoneration is allowed to continue because only one b irr rir ; J AFW tra;,ne is required in accordance with the Note- (1) that ~ mod:,fies the LCO. Although not required, the unit may continue to cool down and initiate RHR. d wbc.h wschele.1 a medor chtojan peg BEAVER VALLEY - UNIT 2 B 3/4 7-2e Amendment No. (ft9esed Oh* 1

' Attachment to Auxiliary Feedwater System INSERT "E" If the inoperable AFW train cannot be restored to OPERAME status within the required completion time, the plant must be placed in a MODE in which the LCO does not apply. To achieve this status, the plant must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. l The allowed completion times are reasonable, based on operating experience, to reach l the required unit conditions from full power conditions in an orderly manner and without i challenging unit systems. L In MODE 4 with one AFW train inoperable, operation is allowed to continue because - only one AFW train, which includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO.- Although not required, the unit may continue to cool down and initiate RHR. BEAVER VALLEY'- UNIT 2 (Proposed Wording) 'I. -

NPFn73 , PLANT SYSTEMS I BASES I 3/4.7.1.2 AUXILIAkY PEEDWATER SYSTEM (AFW) ACTIONS (Continued) e. If all three AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection I headers, the unit is in a seriously degraded condition with no safety related means for conducting a cooldown, and only limited means for conducting a cooldown with nonsafety related equipment. In such a condit!>n, the unit should not be perturbed by any action, including a power change, that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status. ACTION statement e is modified by a Note (3) indicating that all required MODE changes or power reductions are suspended until one AFW train is restored to OPERABLE status. In this case, LCO 3.0.3 is not applicable because it could force the unit into a less safe condition. GSmE. 4) f. With one required AFW train inoperablev action must be taken to immediately restore the inoperable train to OPERABLE status. The immediate completion time is appropriate due to the need to ensure that a safety related means of providing flow to the steam generator (s), for the purpose of core decay heat removal, is available. SURVEILLANCE REQUIREMENTS (SR) The Surveillance Requirements are modified by a General Note which requires that constant communications be established and maintained when any normal AFW pump discharge valve is closed during surveillance testing. SR 4.7.1.2.1 Verifying tht correct alignment for manual, power operated, and automatic valves in the AFW System water and steam supply flow paths provides assurance that the proper flow paths will exist for AFW operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position prior to locking, sealing, or securing. This SR also does not apply to valves that cannot be inadvertently misaligned, such as check valves. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. BEAVER VALLEY - UNIT 2 B 3/4 7-2f Amendment No. (fmgaud W'

NPF=73 , PLANT SYSTEMS BASES 3/4.7.1.2, AUXILIARY FEEDWATER SYSTEM (ADQ SURVEILLANCE REQUIREMENTS (SR) (Continued) SR 4.7.1.2.4 This SR verifies that AFW can be delivered to the appropriate steam generator in the event of any accident or transient that generates an ESFAS, by demonstrating that each automatic valve in the flow path actuates to its correct position on the actual or simulated actuation i signal. The 18 month Frequency is based on the need to perform this l surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. The 18 month Frequency is acceptable based on operating experience and the design reliability of the equipment. gg ,Q g g,eg 9 Qg This SR is modified by a Note (6) that states the SR is not req' tired in MODE 4, In MODE 4, the heat removal requirements would be less providing mors time for operator action to manually align the flow path. SR 4.7.1.2.5 This SR verifies that the AFW pumps will start in the event of any accident or transient that generates an ESFAS by demonstrating that each AFW pump starts automatically on an actual or simulated actuation signal. The 18 month Frequency is based on the need to perform this surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. This SR is modified by two notes. Note (5) indicates that the SR be deferred until suitable test conditions are established for testing the turbine driven AFW pump. This deferral is required because there is insufficient steam pressure to perform the test. Note (6) states that the SR is not required in MODE 4, In MODE 4, the heat removal requirements woula De less providing more time for operator action to manually start the required AFW pump. SR-4.7.1.2.6 cycling each power operated valve (excluding automatic) in the flow path that is not testable during plant operation, ensures that the valves will function when required. The 18 month Frequency is based on the need to perform this surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. BEAVER VALLEY - UNIT 2 B 3/4 7-2h Amendment No. (froposed WOP

ATTACIIMENT H-1 Unit 1 Non-Intent Changes MARKED UP TYPED AG E(S) CilANGE DESCRIPTION REASON FOR CIIANGE 3/47-5

1) ADD footnote (').
1) To clarify that for one steam supply being inoperable requires entry into the ACTION statement a l

3/47-6

1) Delete the words pertaining to
1) Thest words are ao longer one of two steam supplies necessary due to the being inoperable from action additional guidance provided statements d and e.

by footnote (') and the wording contained in the associated Bases Section. 3/4 7 6a -

1) Add words to footnote ")
1) To make the wording of this pertaining to specific footnote consistent with conditions in MODE 4 when equiva!ent footnote contained the surveillances are not in NUREG 1431 Revision 1.

required. B 3/4 7-2c

1) Add words to the LCO Bases
1) Change LCO Bases to reflect penaining to Footnote ('),

addition of footnote ('). B 3/4 7-2d

1) Added words to the Bases for
1) These words were added to ACTION a stating that this reflect the intent of footnote condition does not constitute l'I one AFW train being inoperable.
2) Added words to the Bases for
2) These words make the Bases ACTION pertaining to plant for ACTION a consistent shutdown and MODE 4 with the words in the Bases operation.

for ACTION d.

3) Added words to the Bases for
3) These words make the Bases ACTION b pertaining to plant for Action b consistent with cool down and initiation of the words in the Bases for RHR.

ACTION d.

ATTACIIMENT B-1 _ Unit 1 Non-Intent Changes (Continued) MARKED UP TYPED PAGE(S) CIIANGE DESCRIPTION REASON FOR CIIANGE B 3/4 7-2e

1) Added words to the Bases for
1) These words niake the Bases l

ACTION c pertaining to plant for ACTION c consistent shutdown and MODE 4 with the words in the Base.= operation. for ACTION d. B 3/4 7-2f

1) Revised the first sentence of
1) To make Bases wording this page pertaining to MODE consistent the wording) 4 operation.

contained in footnote I

2) Added the words " MODE 4"
2) This addition clarifies when to the Bases for ACTION f.

the ACTION is applicable. B 3/4 7-2h

1) Added words pertaining to a
1) This change makes the Bases specific condition in MODE 4 wording consistent with the to the Bases for SR 4.7.1.2.4 wording contained in the and SR 4.7.1.2.5.

revised footnote W.

ATTACHMENT B-2 Unit 2 Non-Intent Changes 1 MARKED UP TYPED PAGE(S) CIIANGE DESCRIPTION REASON FOR CIIANGE 3/4 7-4

1) ADD footnote (8)
1) To clarify that for one steam supply being inoperable requires ently into the ACTION statoent a.

3/4 7-5

1) Delete the words pertaining to
1) These words are no longer i

one of two steam supplies necessaiy due to the being inoperable from action additional guidance provided l statements d and e. by footnote (') and the I wording contained in the associated Bases Section. 3/4 7-Sa

1) Add words to footnote (6)
1) To make the wording of this pertaining to specific footnote consistent with conditions in MODE 4 when equivalent footnote contained the surveillances are not in NUREG 1431 Revision 1.

required. B 3/4 7 2c

1) Add words to the LCO Bases
1) Change LCO Bases to reflect pertaining to Footnote (8) addition of footnote (').

B 3/4 7-2d

1) Added words to the Bases for
1) These words were added to ACTION a stating that this reflect the intent of footnote condition does not constitute

(') one AFW train being inoperable.

2) Added words to the Bases for
2) These words make the Bases ACTION pertaining to plant for ACTION a consistent shutdown and MODE 4 with the words in the Bases operation.

for ACTION d.

3) Added words to the Bases for
3) These words make the Bases ACTION b pertaining to plant for Action b consistent with cool dowr4 and initiation of the words in the Bases for RHR.

ACTION d.

NITACitMENT B-2 Unit 2 Non-Intent Changes (Continued) MARKED UP TYPED PAGE(S) CIIANGE DESCRIPTION REASON FOR CIIANGE B 3/4 7-2e

1) Added words to the Bases for
1) These words make the Bases 4

ACTION c pertaining to plant for ACTION c consistent shutdown and MODE 4 with the words in the Bases operation. for ACTION d.

2) Revised the last paragraph of
2) To make Bases wording this page pertaining to MODE consistent the wordingU 4 operation, contained in footnote B 3/4 7-2f
1) Added the words " MODE 4"
1) This addition clarifies when to the Bases for ACTION f.

the ACTION is applicable. B 3/4 7-2h

1) Added words pertaining to a
1) This change makes the Bases f

specific condition in MODE 4 wording consistent with the to the Bases for SR 4.7.1.2.4 wording contained in the and SR 4.7.1.2.5. revised footnote W.

NITACIIMENT C-1 Unit No.1 Typed Technical Specification Pages i

g ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Egmp,yg Insert Index Page XII Index Page XII 3/4 3-19a 3/4 3-19a 3/4 3-27a 3/4 3-2?a 3/4 3-46 3/4 3-46 3/4 3-52 3/4 3-52 3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 3/4 7-6a B 3/4 7-2 B.3/4 7-2 l B 3/4'7-2a B 3/4 7-2b B 3/4 7-2c B 3/4 7-2d B 3/4 7-2e B=3/4 7-2f B 3/4 7-29 3 B 3/4 7-2h B 3/4 7-21 B 3/4 7-2j

DPR-66 INDEX BASES SECTION PAgg 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Va1ves........................... B 3/4 7-1 3/4.7.1.2 Auxiliary Feedwater System.............. B 3/4 7-2 l 3/4.7.1.3 Primary Plant Domineralized Water....... B 3/4 7-2j l _3/4.7.1.4 Activity................................ B 3/4 7-3 3/4.7.1.5 Main Steam Line Isolation Valves........ B 3/4 7-3 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............................. B 3/4 7-4 -3/4.7.3 COMPONENT COOLING WATER SYSTEM.......... B 3/4 7-4 L 3/4.7.4 RIVER WATER SYSTEM...................... B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK...................... B 3/4 7-4 3/4.7.6 FLOOD PROTECTION........................ B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM.................................. B 3/4 7-5 3/4.7.8 SUPPLEMENTAL LEAX COLLECTION AND RELEASE SYSTEM.......................... B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION............. B 3/4 7-5 .3/4.7.12 SNUBBERS................................ B 3/4_7-6 3/4.7.13 AUXILIARY RIVER WATER SYSTEM............ B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 AND 3/4.8.2 A.C. SOURCES, D.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS....... B 3/4 8-1 3/4.9' REFUELING OPERATIONS 3/4.9.1 BORON. CONCENTRATION..................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................... B 3/4 9-1 BEAVER VALLEY - UNIT 1 XII Amendment No.

Q E DPR 66 ' PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION Three Auxiliary gedwater (AFW) trains shall be OPERABLE and 3.7.1.2 consist of the followings a. One motor driven AFW pump with a flow path from WT-TK-10 to each feedwater injection header via the train "A" supply header. b. One motor driven AFW pump with a flow path from WT-TK-10 to each feedwater injection header via the train "B" supply header. c. On3 turbine driven g pump capable of being powered from two ateam supplies with a flow path from WT-TK-10 to each feedwater injection header via the designated train supply header. d. One feedwater injection header to each steam generator. APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator (s) is relied upon for heat removal. ACTION: With one of the two steam supplies to the turbine driven AFW a. pump inoperable, restore two steam supplies to OPERABLE status within-7-days and within 10 days from discovery of failure to meet the LCO or be in HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours, b. With one feedwater injection header inoperable in MODE 1, 2, or 3, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. (1) Only one AFW train (capable ot providing flow to the steam generator (s) relied upon for heat removal), which includes a motor driven pump, is required to be OPERABLE in MODE 4. (8) With one steam supply inoperable, follow ACTION statement a. BEAVER VALLEY - UNIT 1 3/4 7-5 Amendment No. -)

DPR-66 ' PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION fContinued) l With one AFW train inoperable in MODE 1, 2, or 3 for reasons c. other than one of the two steam supplies or one feedwater injection header inoperable, realign the two AFW pumps to separate train supply headers within 2 hours if both train supply headers are operable, and restore the AFW train to OPERABLE status within 72-hours and within 10 days from discovery of failure to meet the LCO or be in 110T STANDBY within the gext 6 hours and in HOT SHUTOOWN within the following 6 hours. d. With two AFW trains inoperable in MODE 1, 2, or 3, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours, e. Uith three AFW trains inoperable in MODE 1, 2, or 3, immediately init action to restore one AFW train 'o OPERABLE status. gte f. With the required AFW train inoperable in MODE 4, immediately initiate action to restore one AFW train to OPERABLE status. SURVEILLANCE REQUIREMENTS - - - - - - - - - - - - - - GENERAL NOTE - - - - - - - - - - - - - - Establish and maintain constant communications between the cont *ol room and the auxiliary feed pump room while any normal AFW amp discharge valve is closed during surveillance testing. y (2) This time period may be ex': ended for up to 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. (3) LCO 3.0.3 and all other LCO ACTION statements requiring MODE changes are suspended until one AFW train is restored to OPERABLE status. BEAVER VALLEY - UNIT 1 3/4 7-6 Amendment No.

DPR-B6 ' PLANT SYSTEMS SURVEILLiNCE REQUIREMENTS (continued) 4.7.1.2.1 Verify each AFW manual, power operated, and automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven AFW pump, that is not locked, scaled, or otherwise secured in positig, is in the correct position at least once per 31 days 4.7.1.2.2 Verify operability of each River Water Auxiliary Supply valve by cycling each manual River Water to Auxiliary Feedwater System valve through one complete cycle at least once per 31 days. 4.7.1.2.3

Verify, at the frequency specified in the Inservice Testing Program, on a STAGGERED TEST BASIS that the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head as specified in the Inservice Testing Program.

The provisions of Specification 4.0.4 are not applicable for i i entry i 3 for the steam turbine driven pump testing. g MODE 4.7.1.2.4 Verify each AFW automatic valve that is not

locked, sealed, or otherwise secured in position, actuates to the correct position on an actual og simulated actuation signal at least once por 18 months 4.7.1.2.5 Verify each AFW pump starts automatically on an actual or sin actuation signal at least once per 18 months.ggtgd 4.7.1.2.6 Cycle each power operated (excluding automatic) valve in the flow path that is not testable during plant operation, through at least one complete cycle at least once per 18 months during shutdown.

4.7.1.2.7 Verify AFW flow from WT-TK-10 to the Steam Generators with the AFW valves in their normal alignment. W (4) Reverify these requirements by a second and independent operator. (5) Not required to be performed for the turbine driven AFW pump until 24 hours after establishing the minimum required secondary side steam pressure of greater than 600 psig. (6) Not applicable in MODE 4 when steam generator (s) is relied upon for heat removal. (7) This surveillance is required to be performed prior to entry into MODE 2 whenever the plant has been in MODES 5 or 6 for greater than 30 continuous days. BEAVER VALLEY - UNIT 1 3/4 7-6a Amendment No.

DPR-66 ' PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) LCO (Continued) for all events accompanied by a loss of offsite power and a single failure. This is accomplished by powering two of the pumps from independent emergency buses. The third AFW pump is powered by a different means, a steam driven turbine suppl:.ed with steam from a source that is not isolated by closure of the main steam isolation valves (MSIVs). The AFW System is configured into three trains. The ArW System is considered OPERABLE when the components and flow paths required to l p r o v i d e -- r e d u n d a n t ATM flow to the steam generators are OPERABLE. This requires that the two.sotor driven AFW pumps be OPERABLE in two diverse paths, each supplying AFW to each steam generator. The turbine driven AFW pump is required to be OPERABLE with redundant steam supplies from two of the three main steam lines upstream of the MSIVs, and shall be capable of supplying AFW to the steam generators via the designated train supply header. The

piping, valves, instrumentation, and controls in the required flow paths also are required to be OPERABLE.

The LCO is modified by two notes. Note (1) indicates that one AFW train (capable of providing flow to the steam generator (s) relieu upon for heat removal), which includes a motor driven pump, is required.to be OPERABLE in MODE 4. This is because of the reduced heat removal requirements and short period of time-in MODE 4 during which the AFW may be required and the insufficient steam available in MODE 4 to power the turbine driven AFW pump. Note (8) states that with one steam supply inoperable,. follow ACTION statement a. This condition does not constitute one AFW train being inoperable. The train associated with the turbine driven AFW pump continues to be capable of performing its intended function assuming no failure of the remaining OPERABLE steam supply. APPLICABILITY In MODES 1, 2, and 3, the AFW System is required to be OPERABLE in the event that it is called upon to function when the MFW is lost. In addition, the ATW System is required to supply enough makeup water to replace the steam generator secondary inventory lost as the unit cools to MODE 4 conditions. In MODE 4, the AFW System may be used for heat removal via the steam generators. In MODE S or 6, the steam generators are not normally.used for heat removal, and the AFW System is not required. BEAVER VALLEY - UNIT 1 B 3/4 7-2c Amendment No.

DPR-66 PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) (Continued) ACTIONS a. If one of the two steam supplies to the turbine driven AFW train is inoperable, action must be taken to restore OPERABLE status within 7 days. The 7 day completion time is reasonable, based on the following reasons: 1. The redundant OPERABLE steam supply to the turbine driven AFW pump; 2. The availability of redundant OPERABLE motor driven AFW pumpo; and 3. The low probability of an event occurring that requires the inoperable steam supply to the turbine driven AFW pump. This condition does not constitute one AFW train being inoperable. The second completion time for ACTION statement a establishes a limit on the maximum time allowed for any combination of conditions to be inoperable during any continuous failure to meet this LCO. The 10 day completion time provides a limitation time allowed in this specified condition after discovery of failure to meet the LCO. This limit is considered reasonable for situations in which ACTION statements a and c are entered concurrently. The AllQ connector between 7 days and 10 days dictates that both completion times apply simultaneously, and the more restrictive must be met. If the inoperable steam supply cam.t be restored to ? OPERABLE status within the required spletion time, the plant must be placed in a MODE in which the LCO does not apply. Tc chieve this status, the plant must be placed in at least MODE 3 within 6 hours, and in MODE 4 w;. thin the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions trom full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with one steam supply inoperable, operation is allowed to continue because only one AFW

train, which includes a motor driven pump, is required in accordance with BEAVER VALLEY - UNIT 1 B 3/4 7-2d Amendment No.

DPR-66 ' PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY PEEDWATER SYSTEM (AFW) ACTIONS (Continuedt Hote (1) that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR. 1 b. With one feedwater injection header inoperable in MODES 1, 2, or 3, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without i challenging unit systems. In MODE 4 with one feedwater injection header inoperable, operation is allowed to continue because only two steam generatoro are required to remove decay heat per LCO 3.4.1.3, "RCS-SHUTDOWN." Although not required, the unit may continue to cool down and initiate RHR. c. With one of the required AFW trains (pump or flow path) inoperable in MODE 1, 2, or 3 for reasons other than ACTION statements a or b,-action must be taken to restore OPERABLE status within 72. hours. This condition includes the loss of two steam supply lines to the turbine driven AFW pump. The 72 hour completion time is reasonable, based on redundant capabilities afforded by the AFW System, time needed for repairs, and the low probability of a DBA occurring during this time period. i The second complecion time for ACTION statement c establishes a limit on the maximum time allowed for any combination of conditions to be inoperable during any continuous failure to m3et this LCO. The lo day completion time provides a limitation time allowed in this specified condition after discovery of failure to meet the LCo. This limit is considered reasonable for situations in which ACTION statements a and c are entered concurrently. The AHQ connector between 72 hours and 10 days dictates that both completion times apply simultaneously, and the more restrictive must be met. If the inoperable AFW train cannot be restored to OPERABLE status within the required completion time, the plant must be placed in a MODE in which the LCO does not apply. To BEAVER VALLEY - UNIT 1 B 3/4 7-2e Amendment No. =.

O DPR*66 'ELMIT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) ACTIONS (Continued) achieve this status, the plant must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with one AFW train inoperable, operation is allowed to continue because only one AFW

train, whicn includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO.

Although not required, the unit may continue to cool down and initiate RHR. ACTION statement c is modified by a note. Note (2) states that the completion time of 6 hours to reach HOT SHUTDOWN may be extended for an additional 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. This extension of the required completion time to reach MODE 4 from MODE 3 to 96

hours, allows additional time to complete any necessary repairs and/or testing of the turbine drivan AFW pump prior to initiating a plant cooldown to MODE 4.

d. When two AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with two AFW trains inoperable, operation is allowed to continue because only one AFW

train, which includes a motor driven pump, is required in accordance with the Note (1) that modifies the LCO.

Although not required, the unit may continue to cool down and initiate RHR. e. If all three AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit is in a seriously degraded condition with BEAVER VALLEY - UNIT 1 B 3/4 7-2f Amendment No.

0 DPR-66 ' PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) ACTIONS (C.gatinued) no safety related means for conducting a cooldown, and only limited means for conducting a cooldown with nonsafety related equipment. In such a condition, the unit should not be perturbed by any action, including a power change that might result in a trip. The a viousness of this con,dition requires that action be started immediately to restore one AFW train to OPERABLE status. ACTION statement e is modified by a Note (3) indicating that all required MODE changes or power reductions are auspended until one AFW train is restored to OPERABLE status. In this case, LCO 3.0.3 is not applicable because it could force the unit into a less safe condition. f. With one required AFW train inoperable in MODE 4, action must be taken to immediately restore the inoperable train to OPERABLE status. The immediate completion time is appropriate due to the need to ensure that a safety related means of providing flow to the steam generator (s), for the purpose of core decay heat removal, is available. SURVEILIANCE REOUIREMENTS (SR) The Surveillance Requirements are modified by a General Note which requires that constant communications be established and maintained when any normal AFW pump discharge valve is closed during surveillance testing. SR 4.7.1. M Verifying the correct alignment for manual, power operated, and automatic valves in the AFW System water and steam supply flow paths provides assurance that the proper flow paths will exis,t for AFW operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position pr'sr to locking, sealing, or securing. This SR also does not apply to valves that cannot be inadvertently misaligned, such as check valves. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable 'of being micpositioned are in the correct position. The 31 day frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions. Note (4) ensures valve position verification is reverified by a second and independent operator. BEAVER VALLEY - UNIT 1 B 3/4 7-2g Amendment No. L-

O DPR-66 PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) $_URVEILLANCE REOUIREMENTS (SR) (Continued) SR 4.7.1.2.2 Varifying the operability of each river water auxiliary supply valve by operating the valves through one complete cycle at least once per 31 days, ensures that an alternate water source will be available if the water volume in the demineralized water storage tank is depleted during system operation as a result of a DBA. SR 4.7.1.2.3 Verifying that each AFW pump's developed head at the flow test point is greater than or equal to the required developed head ensures that AFW pump performance has not degraded during the cycle. The term " required developed head" refers to the value that is assumed in the AFW safety analysis for developed head at a flow point. This value for required developed head at a flow point is defined as the Minimum Operating Point (MOP) in the Inservice Testing Program. Flow and differential head are normal test parameters of centrifugal pump performance required by Section XI of the ASME Code. Because it is undesirable to introduce cold AFW into the steam generators while they are operating, this testing is normally performed on recirculation flow. The recirculation flow rate is assumed to be a fixed value since the recirculation line flow resistance remains constant. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. Performance of inservice testing as required in the ASME Code, Section XI, satisfies this requirement. This SR is modified by a Note (5) indicating that the SR should be deferred until suitable test conditions are established for testing the turbine driven AFW pump. This deferral is required because there is insufficient steam pressure to perform the test. SR 4.7.1.2.4 This SR verifies that AFW can be delivered to the appropriate steam generator in the event of any accident or transient that generates an ESFAS, by demonstrating that each automatic valve in the flow path actuates to its correct position on the actual or simulated actuation signal. The 18 month Frequency is based on the need to perform this surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. The 18 month Frequency is acceptable based on operating experience and the design reliability of the equipment. BEAVER VALLEY - UNIT 1 B 3/4 7-2h Amendment No.

__ _. _ - - ~ _ _ O DPR-66 PLANT SYSTEMS BASES M_4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) SURVEILLANCE REOUIREMENTS (SR) (Continued) This SR is modified by a Note (6) that states the SR is not required in MODE 4 when steam generator (s) is relied upon for heat removal. In MODE 4, the heat removal requirements would be less providing more time for operator action to manually align the flow path. SR 4.7.1.2.5 This SR verifies that the AFW pumps will start in the event of any accident or transient that generates an ESFAS by demonstrating that each AFW pump starts automatically on an actual or simulated actuation signal. The 18 month Frequency is based on the need to perform this surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. This SR is modified by two notes. Note (5) indicates that the SR be deferred until suitable test conditions are established for testing the turbine driven AFW pump. This deferral is required because there is insufficient steam pressure to perform the test. Note (6) states that the SR is not required in MODE 4 when steam generator (s) is relied upon for heat removal. In MODE 4, the heat removal requirements would be less providing more time for operator action to manually start the required AFW pump. SR 4.7.1.2.6 cycling each power operated valve (excluding automatic) in the flow path that is not testable during plant operation, ensures that the valves will function when required. The 18 month Frequency is based on the need to perform this surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. SR 4.7.1.2.7 This SR verifies that the AFW is properly aligned by verifying the flow from WT-TK-10 to the steam generators prior to entering MODE 2 after more than 30 continuous days in MODE 5 or 6 per Note (7). OPERABILITY of AFW flow paths must be verified before sufficient core heat is generated that would require the operation of the AFW System during a subsequent shutdown. The Frequency is reasonable, based on engineering judgment and other administrativo controls that ensure that flow paths remain OPERABLE. To further ensure AFW System alignment, flow path OPERABILITY is verified following extended BEAVER VALLEY - UNIT 1 B 3/4 7-21 Amendment No.

t ,o 1 DPR'66 PLANT SYSTEMS f BASES 3/4.7.1.2 -AUXILIARY PEEDWATER SYSTEM (AFW) SURVEILLANCE REQUIREMENTS ( SR) ' (Continued) outages to determine no misalignment of valves has occurred. This SR ensures that the flow path from the WT-TK-10 to the steam generators is properly aligned. ] 3/4.7.1.3 PRIMARY PLANT DEMINERALIZED WATER The OPERABILITY of the PPDW storage tank with the minimum water volume ensures-that sufficient water is available for cooldown of the Reactor Coolant System to less than 350'F in the event of a total loss of off-site power. The-minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 9 hours with steam discharge to atmosphere. t i I 1 j i i 1 i BEAVER VALLEY - UNIT 1 B 3/4 7-2j Amendment No. l e ,.,...._m. _ _. _.,, _ _ _. - _.,,.,. _ _, ~ -.= ,,,-,,-m.~.._..--

L ATTACIIMENT C-2 \\ Unit No. 2 Typed Technical Specification Pages Ie

.g.- s ' ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE No. NP M 'DCCKET NO. 50-412 Replace the following pagestof Appendix A,: Technical Specifications, with-the enclosed pages as. indicated. The revised pages are identified 1by :cmendment number. and contain vertical lines indicating

the-areas of change.

Remove Ine3r1 3/4 3-20 3/4 3-20 3/4 3-27 3/4 3-27 i 3/4 3-36 3/4 3-36 l 3/4 3 3/4 3-37 3/4 3-54 3/4 3-54 j 3/4 3-59 3/4 3-59 L 3/4 7-4 3/4 7-4 3/417-5 3/4.7-5 3;4 7-Sa B 3/4 7-2 B 3/4 7 - 1 B 3/4 7-2a B 3/4 7-2b B 3/4 7-2c B-3/4 7-2d-B 3/4-7-2e B 3/4.7-2f -B 3/4 7-2g-1 B 3/4 7-2h-B 3/4 7-21 3 3/4 7-2j 1

NPF-73

  • ELANT SYSTEMS AUXILIARY FEEDWATER SYSTEM

,IMITING CONDITION-FOR OPERATION L

3. 7.1. 2 -

Three Auxiliary F and consist of the following: ydwater - (AFW) ' rains shall be OPERABLE c a. One motor driven AFW pump with a flow path from TK-210 to each feedwater injection header via the train "A" supply header. b. One motor driven AFW pump with a flow path from TK-210 to each feedwater injection header via the train "B" supply header. c. One turbine driven g W pump capable - of being powered from two steam supplies with a flow path from TK-210 to each feedwater injection header via the designated train supply header. d. One feedwater injection header to each steam generator. APPLICABILITY. MODES 1, 2, and 3, MODE 4 when steam generator (s) is relied upon for l heat removal. ACTION: a. With one of the two steam supplies,to the turbine driven AFW pump inoperable, restore two steam supplies to OPERABLE status within 7 days and within 10 days from discovery of failure to meet the LCO or be in HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. b. With one feedwater injection header inoperable.in MODE 1, 2, or ?, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours. (1) Only one AFW train (capable of providing flow to the steam generator (s) relied upon _ for heat removal), which includes a motor driven pump, is requiru. to be OPERABLE in MODE 4. (8) With one steam supply inoperable, follow ACTION statement a. BEAVER VALLEY - UNIT 2 3/4 7-4 Amendment No.

NPF-73 PLANT SYSTEMS

LIMITING-CONDITION FOR OPERATION ACTION (Continued)

With one AFW train inoperable in MODE 1, 2, or 3 for reasons c. other than one of the. two steam supplies or'one feedwater injection header inoperable, realign the two AFW pumpn to separate train supply headers within 2 hours if both train supply headers are operable, and restore the AFW train to OPERABLE status within 72 hours and within 10 days from discovery of failure to meet the LCO or' be in HOT. STANDBY within the gext 6 hours and in HOT SHUTDOWN within the following 6 hours. d. With two AFW trains inoperable in MODE 1, 2, or 3, be in HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours, e. With three AFW trains inoperable in MODE 1, 2, or 3, immediately _init action to restore one AFW train to OPERABLE status.gte -f. With the required AFW train inoperable in MODE _4, -immediately. initiate action to restore one AFW train to OPERABLE status. l 5URVEILLANCE REQUIREMENTS - - - - - - - - - - - - - - GENERAL NOTE - - - - - - - - - - - - - - Establish and maintain : constant-communications. between the control room and the auxiliary feed pump room while any - normal AFW pump discharge valve is closed during surveillance testing. (2) This time period may be extended for up to 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2_following a refueling outage. _(3 ) _ LCO - 3. 0. 7 a nd all other LCO ACTION statements requiring MODE changes ace s*1spended until one AFW train is--restored to OPERABLE status. BEAVER VALLEY - UNIT 2 3/4~7-5 Amendment No. 1

NPF-73 L>LANT-SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.1.2.1' Verify each AFW manual, power operated,.and automatic valve in each water flow path,_and in both-steam supply flow paths to the steam turbine driven AFW pump, that is not locked, riealed, or otherwise secured in posit in the correct position at least once per 31 days. g is 4.7.1.2.2 Verify operability of each Service Water Auxiliary Supply valve by cycling each - manual Service. Water to Auxiliary Feedwater System valve through one complete cycle at least once per 31 days. I 4.7.1.2.3

Verify, at the frequency specified in the Inservice Testing Program',

on a STAGGERED TEST BASIS that the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head as specified in the Inservice Testing Program. The provisions of Specification 4.0.4 are not applicable for entry i 3 for the steam turbine driven pump testing. gig MODE 4.7.1.2.4 - Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or achadon signal at least once per - 18 months (,)dadated 4.7.1.2.5 Verify each AFW pump starts automatically on an actual or simulat months. g g etuation signal at least once per 18 4.7.1.2.6 Cycle each power operated (excluding automatic) valve in the flow path that is not testable during plant operation, through at least'one complete cycle at least once per 18 months during shutdown. 4.7.1.2.7 Verify AFW flow from TK-210 to the Steam Generators with the AFW valves in-their normal alignment Ill (4) Reverify these requirements by a second and independent operator. (5) Not - required to be perforued for the turbina driven AFW pump until 24~ hours after establishing the minimum required secondary side steam pressure of greater than 600 psig. (6) Not applicable. in MODE 4 when steam generator (s) is relied upon for heat removal. (7) This surveillance is required to be performed prior to entry into MODE 2 whenever the plant has been in. MODES S or 6 for greater than 30 continuous days. BEAVER VALLEY - UNIT 2 3/4 7-Sa Amendment No. i J

g, v. t*r hPF D .fLANT SYSTEMS -. BASES - 3 / 4. 7.1. 2 -- AUXILIARY FEEDWATER SYSTEM ~ (AFW); LCO-(Continued)- requires that the two motor _ driven AFW pumps be OPERABLE in two-diverse f. paths, each supplying AFW to each steam generator. The turbine driven : AFW pump - is: required to be OPERABLE with redundant steam supplies from at least ' two of the three main steam lines -upstream of the,MSIVs, and shall'be capable:-of. supplying.AFW to the _ steam. generators via the designated train supply header.-'The piping, valves,' instrumentation,_.and controls in the required flow paths also 'are. required-totbe OPERABLE. The LCO ;is: modified by two notes. Note (1) indicates that one AFW Ltrain -(capable of providing flow to the steam generator (s) relied _'upon'.for heat. removal), which includes a motor driven' pump, is required to be' OPERABLE in MODE 4. This is because of:the reduced heat removal requirementssand-short period of time in MODE 4Lduring lL which the AFW may be_ required and the insufficient steam available in. l-

MODE:4-to power the-turbine driven AFW pump.

Note. (8) ~ states that L with oneisteam' supply finoperable, follow ACTION-statement. a. This l condition does ; not constitute one AFW train being ~ inoperable. The train.. associated :with the turbine driven ' AFW pump continues ' to be capable L of' performing _ its intended. function ' assuming no fallure -of -_the remaining OPERABLE steam supply. APPLICABILITY In MODES 1,; 2, and 3, the AFM '. System - is required to lbe < OPERABLE :.in the event.that it is calledcupon to-function'when the MFW:is! lost. In addition, the-AFW-System is_ required to' supply-enough-makeup-water-to' replace.the steam generator-secondary-. inventory! lost as the-unit-cools yo MODE 4 conditions. In{ MODE:4,_theEAFW System may be used for heat removal via the steam-generators.. In-MODEE5;or-6, the steam generators are-not normally used for heat- -removal, and the AFW System _is'not required. ACTIONS a. If one of the two steam supplies to tha' turbine driven AFW train 11s inoperable, action.must-be taken to restore OPERABLE status within 7 days. The 7-day completion time is reasonablei based on the following reasons:-

1. --

The redundant: OPERABLE steam supply to the turbine ! driven AFW pump; ' BEAVER. VALLEY - UNIT 2 -B 3/47-2c_ Amendment No.

NPF ~)3 PLANT SYSTEMS BASES -3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) ACTIONS (ContinueG 2. The availability of redundant OPERABLE motor driven AFW pumps; and. 3. The low probability of an event occurring that requires the inoperable steam supply to the turbine driven AFW pump. This condition does not constitute one AFW train being inoperable. The second completion time for ACTION statement a establishes a limit on the maximum time allowed for any combination of. conditions to be inoperable during any continuous failure to meet this LCO. The 10 day completion time provider a limitation time allowed in this specified condition after discovery of l failure to meet the LCO. This limit is considered reasonable for situations in which ACTION statements a and c i are entered concurrently. The AHQ connector between 7 days and 10 days dictates that both completion times apply simultaneously, and the more restrictive must be met. If the inoperable steam supply cannot be restored to OPERABLE status within the required completion time, the plant must be placed in a MODE in which the LCO does not apply. To achieve this status, the plant must be placed in at Joast JE 3 within 6 hours, and in MODE 4 within the following,. hours. I The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with one steam supply inoperable, operation is allowed to continue because only one AFW train, which includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR. b. With one feedwater injection header inoperable in MODES 1, 2, or 3, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3. within 6 hours, and in MODE 4 within the following 6 hourd. BEAVER VALLEY - UNIT 2 B 3/4 7-2d Amendment No.

. v: 3 ll ' _ ~, 'NPF PLANT SYSTEMS BASES-3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) JACTIONS (Continued) .The allowed completion times are reasonable, based on -operating _ experience,1to reach the required unit conditions from-full power conditions in an orderly manner and without challenging unit-systems. In MODE 4_ with one feedwater injection haader inoperable, operation is allowed -to continue because only two steam generators' are required.to remove decay heat per LCO 3.4.1.3, "RCS-SHUTDOWN." Although not required, the unit may continue to cool down and initiate RHR. With one of the required ~ AFW trains- (pump or flow path) c. --inoperable in MODE 1, 2, or 3 for reasons other than ACTION-statements a or b, action must be taken-to-restore OPERABLE -status within 72 hours. This condition includes tho' loss-of two steam supply lines to the turbine driven'AFW pu::.p. The 72 hour completion time is reasonable, based on redundant = 1 L capabilities afforded. by the AFW - System, time needed for l repairs, and the-low probability-of a DBA occurring during [ this_ time period. The second completion; time.for ACTION statement- .c establishes-a limit on the. maximum time allowed for any combination or conditions to be -inoperable during any continuous failure to. meet this LCO. The-10_ day completion: time provides a-limitationi time allowed in this. specified condition'- after discovery._ of failure to meet the LCO. This limit is considered-reasonable for situations.in which ACTION statements a and c Lare entered concurrently._ -The AHQ _ connector between 72 hours and 10 days-dictates that'both completion times apply simultaneous 1e, and the more restrictive must be met. It. the inoperable - AFW train cannot - be restored to - OPERABLE status within the required _ completion time,-the plant must- ~ be placed in s a : MODE. in' which the LCO does not apply.- -To achievecthis status,- the plant musti be placed in-at'least MODE'3 within 6 hours, and in MODE 4 within the-following 6 hours. The allowed' completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging-unit systems. ,; BEAVER-VALLEY _- UNIT 2 B 3/4 7-2e Amendment No. i

-.o NPF ~/3 -PLANT SYSTEMS BASES-3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) ACTIONS (Continued) In MODE 4 with one AFW train inoper.able, operation is allowed to-continue because only one AFW

train, which includes a motor driven pump, is required in accordance with Note (1) that modifies the LCO.

Although not required, the unit may continue to cool down and initiate RHR. ACTION statement c is modified by a note. Note (2) states that the completion time of 6 hours to reach HOT SHUTDOWN may be extended for an additional 90 hours for the turbine driven AFW pump provided that the plant has not entered MODE 2 following a refueling outage. This extension of the l required completion time to reach MODE 4 from MODE 3 to 96 i

hours, allows additional time to complete any necessary I

repairs and/or testing of the turbine driven AFW pump prior j to initiating a plant cooldown to MODE 4. 1 l d. When two AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4 within the following 6 hours. The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4 with two AFW trains inoperable, operation is allowed to continue because only one AFW train, which includes a motor driven pump, is required in accordance with the Note (1) that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR. e. If all three AFW trains are inoperable in MODE 1, 2, or 3 for reasons which may include the feedwater injection headers, the unit is in a seriously degraded condition with no safety related means for conducting a cooldown, and only limited means fcr conducting a cooldown with nonsafety related equipment. In such a condition, the unit should not be perturbed by any action, including a power change, that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status. BEAVER VALLEY - UNIT 2 B 3/4 7-2f Amendment No.

j-6: 4; [dl NPF-13-- FLANT. SYSTEMS BASES 3/4.7.1.2-AUXILIARY FEEDWATER SYSTEM (AFW) ACTIONS (Continued) ACTION statement e is modified by a Noth (3) indicating that all required-MODE changes or power reductions are suspended until one AFW train is restored to OPERABLE-status. In this case, LCO 3.0.3 is not applicable because it could force the unit into a less safe condition. f. With one-required AFW - train inoperable in MODE 4, action must be taken to immediately restore the inoperable train to OPERABLE status. The immediate completion time-is appropriate due to the need to ensure'that a safety related means - of providing flow to the steam generator (s), for the purpose of core decay heat removal, is available. SURVEILTANCE REOUIREMENTS (SR) The Surveillance - Requirements are modified by a General Note, which-- requires that constant communications be established and ' maintained when any normal AFW pump-discharge valve is closed during surveillance testing. SR 4.7.1.2.1 Verifying the correct - alignment for manual, power operated, -and automatic valves in_the AFW System water and steam supply flow paths provides assurance that the proper flow paths will exist for - AFF operation.- This SR does not-apply to valves-that-are locked,-sealed, or otherwise-secured-in position, since they are verified to be-in the correct position prior to locking, sealing,-or securing.- This-SR also does not apply _to. valves that cannot-be inadvertently misaligned, such as check valves. This SR does not T require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.. The-31 day. frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions. Note (4) ensures valve position verification is reverified by a second and independent operator. SR 4.7.1,'2.2 , Verifying the operability of each service water auxiliary supply valve by operating the. valves - through one-complete cycle ' at least once' per 31 days, ensures that an alternate water source will be available if the water volume in the domineralized water storage tank is depleted-during system operation as a result of a DBA. _ BEAVER VALLEY-- UNIT _2 B 3/4 7-2g Amendment No.

3y = n g- 'NPF-73 PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW) -SURVEILLANCE-REOUIRFMENTS (SR) (Continued) =SR-4.7.1.2.3 Verifying that each AFW pump's_ developed head at the flow test _ point -is'greaterithan or aqual to the required developed-head ensures that-AFW - pump. performance has not ; degraded ' during the cycle. The term " required ^ developed head" refers to the value that is assumed in the .-AFW safety, analysis for-developed head at a flow-point. This value ifor required developed head _at a flow point is_ defined as=the Minimum-s Operating ' Point.(MOP) in the Inservice Testing Program. Flow and differential head are normal _ test parameters of centrifugal-pump -performance required by Section-XI of the ASME Code.-- BecLuse it is undesirable - to introduce cold AFW into the steam generators while u they are operating, this.. testing is-normally_ performed on l recirculation flow. This' test confirms one point'on the pump design curve and is indicative of'overall performance. :Such inservice tests confirm component CPERABILITY, trend performance, and detect l incipient failures by indicating abnormal performance. Performance of inservice testing.as required in the ASME Code, Section XI, satisfies this requirement. ThisLSR-'is modified by a Note (5) indicating that the SR should be deferred until suitable test conditions are established ifor _ testing the-turbine driven AFW pump. This-deferral is required because there is insufficient steam-pressure to perform-the test. SR 4.7.1~.2.4 This SR verifies that AFW can be delivered toithe appropriate steam generator in-the event of-any tecident or transient that generates an ESFAS, by-demonstrating that each automatic valve in the flow path actuates to its correct position on the actual or simulated actuation signal.-lThe 18 month Frequency is based on the need to perform this surveillance:under the conditions that apply during a unit outage and the' potential _ for an unplanned transient -if the surveillance were iperformed :with ' the r e a'c t o r :a t p o w e r. The 18 month Frequency -is ' acceptable ' based on operating experience and the design reliability of the equipment. -This SR is modified by a Note (6) that states the SR is not required in1 MODE 4 when-steam : generator (s) is relied upon for heat removal. 3 In MODE 4, the heat-removal requirements would be less providing more time for operator action'to manually _ align the flow path. BEAVER VALLEY-- UNIT 2 B 3/4 7-2h Amendment No.

..7

['

.NPF-73 " PLANT SYSTEMS BASES -- 3 / 4. 7.1. 2 AUXILIARY FEEDWATER SYSTEM (AFW) 1

SURVEILLANCE REOUIREMENTS-(SR)- (Continued)

~ -SR 4.7.1.2.5 - This '- SR __ verifies that l the AFW pumps will staTt in the event of any accident - or = transient that generates : an-ESFAS by demonstrating that each AFW-pump starts automatically' on an actual or-simulated- - actuation signal.- The -18 month - Frequency is-based on L the need-to-perform ! this surveillance under the-conditions that - apply during a -unit outage and the potential for an unplanned: transient if the surveillance were performed with the reactor at power. l This>SRLis-modified by two notes.-- Note- (5) _ indicates that-the SR be E -deferred until suitable test ~ conditions are established for testing. -the: turbine driven AFW pump. This deferral is required-because-there -is; insufficient steam pressure to perform the test. Note (6)-- states . that the SR -. is : not required in MODE. 4 when= steam generator (s) -_ is

relied.upon for heat ' removal.

LIn MODE 4, t.he - heat removal requirements _would be:less providing more time for operator action to-manually start the required AFW pump. SR 4.7.1.2.6 Cycling: each - power _ operated valve --'(excluding --. automatic) in: the flow path that is not - testable during plant operation, ensures 1that the valves wi?1 function when required.: The 18. month Frequency'is based .on the.need - to perform this surveillance-under -the conditions that apply -during =a unit outage and-the-. potential for an _ unplanned. transient if- - the surveillance-were performed with the reactor :at power. SR 4.7.1.2.7 This SR verifies that the _ AFW is properly aligned by_ verifying the flow _, f rom TK-210 to - the - steam generators prior to entering MODE 2 af ter. ~ more -than - 30 continuous days in-- MODE 5 or 6 per Note (7).

OPERABILITY ofTAFW flow' paths must be-verified before sufficient core
heatais_ generated thatLwould-require the. operation _of the AFW System during a' subsequent shutdown.

The Frequency is reasonable, based'on engineering l judgment ' andj other administrative controls-that ensure that, flow paths remain - OPERABLE. -To further ensure _AFW System alignment, flow ~ path' OPERABILITY. ia verified following extended . outages to determine _no misalignment of valves has occurred. This SR -ensures--that the flow path from the-TK-210-to the steam generators is= properly aligned. . BEAVER VALLEY - UNIT-2 B 3/4 7-21 Amendment No. y +, n

,o.' d' o LTP$-73 PLANT SYSTEMS BASES 3/4.7.1.3 PRIMARY PLANT DEMINERALIZED WATER (PPDW) The OPERABILITY of the PPDW storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at liOT STANDBY conditions for 9 hours with steam discharge to atmosphere. Jf4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 0.35 gpm primary-to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the accident analyses. l BEAVER VALLEY - UNIT 2 B 3/4 7-2j Amendment No. l _}}

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