ML20065N483
| ML20065N483 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/24/1993 |
| From: | Hux R UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20065N458 | List: |
| References | |
| OTO-RK-00001, OTO-RK-1, NUDOCS 9404270193 | |
| Download: ML20065N483 (97) | |
Text
{{#Wiki_filter:Enclosure 7 Total of 97 pages [ 33
/e TEMPCcAQV CHA W M'l(E Q(CUE 5' TO29 TCN NO. N" A 1 P200EDURE NUMSER M7[I"b((N REVISICh NO. b PROCECURE TITLE l DSS CY [97thtl bEM NWed 1.1 One Time TCN: YES _ N0 d Effectwe from 4A. t o _ 2}4,
- 2. CHANGE
SUMMARY
bgl, M / f [# Affh5 2. 7hW/6 2.1 PAuE hUMBERS AFFECTED BYf CliANGE I _h t TM' I#r M /7
) 2.2 CESCRIPTION OF CHAN3E . N N / I ' I/// A 8 8 M br NM AM 9 2.3 REASON FOR CHANGE ,bd [/71/ bN Mf/.f [ M M M M r M N U M 7.g\%*f
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- 3. 10CFR $0.59/50.54(P)(Q) APDLICAB:LITY - THIS TCN REPRESENTS:
T.p t W6 3.1 *YES NO /_ A proposed change to the f acility as described in the ** t
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3.2 "YES _ N0 f A change to procedures as described in the FSAR? 3.3 *rES _ NO /_ A test or experiment not described in the FSA y (, (.7.g,\h'(9 e l6 3.4 *YES _ N0 s A cnange to the Technical Specifications? u 3.5 *YES._. 3.6 "Y ES _ N C /_._ A change affecting the environment or the NPDES Permit N0 4 A change which affects the RERP? 6 ' g Q -
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a 3.7 **YES _ NO A change which affects the Security Plan? p 3.8 YES _ h0 Z A changf ,r which a licensing Document Change has been initiated? f '71.4. 3.9 **YES __ NO d A change reauiring a new/ revision to a Surviellance Task Sheet Approval fem? 3.10 'YES _ NO 4 A change affecting the Offsite Dose Calculation Manual (CDCM), the Process Control Program (PCP), or Core Operating Limits Repert (COLR).
*Yes redires a procedure revision. TCN is not allowed.
"YES resuires Emergency Preparedaess or Security Department evaluation.
] frYes Refer to APA-ZZ-00340 for instructions.
- 4. PREPARED BY #M1 M O*/8"N8 SIGNATURE TITLE CME
- 5. QUALIFIED REVIEWER
- M2 k C SIGNTiuaE TITLE / CAT [ ]
- 6. PRELIMINARY APPROVAL (Prior to Implem ~ ati- g 6.1 SEh!OR REACTOR OPERATOR ~ "
b db // Y' O SMINATURE TITLC CATE
- 7. FlhAL APPROVAL (Within 14 Days of Imnlemytation) 7.1 APPROVAL AUTHORITY SIGNATURE TITLE DATE U,
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TEMPORARY CHANGE N0YICE REQUEST FORM
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- 1. PROCEDURE NUMBER 978 ~ #fa 6tW/> / REVISION NO. 1 1
PROCEDURE TITLE $.0$S ff MM72R NtX4 NAA)1S 1.1 One Tir TCN: YES ._ NO ./_ Effective from 7M- to -7h*-
- 2. CHANGE SUMHARY Saga 49lS~ hf MS A 7)lrtf/6 2.1 PAGE NUMBERS AFFECTED BY CHANGE M f//f M AM/7
" 2.2 GESCRIPTION OF CHANGE Ad/d & PCAV MD/ # Fir-//h)Wrez)//kff _ Y f[7~Wtb 8AA// -0 HZ 72*J1A r*//Aktshk)/2DF - 2.3 REASON FCR CHANGE /P h/ /M8 e/AM rY # CJ' b-/N2 WN1hd/2ff nAnmd / Av & PT2-3ML ~,
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assue o $ 3. 10CFR S0.59/SO.54(P)(Q) APPLICABILITY - THIS TCN REPRESENTS: (Q#
, I 3.1 'YES _ NO [ A proposed change to the facility as described in the FSAR? ' UN O 11993 3.2 *YES _ NO / A change to procedures as described in the FSAR? ( s ,-
3.3 'YES _ NO A test or experiment not described in the FSAR? r 3.4 "YES ,,_ NO g A enange to the Technical Specifications? *N ACCCusTABLE 3.5 *YES _ NO A change af fecting the environment or the NPCES Perpety ,- HOLO 8 3.6 **YES _,. NO . A change which affects the RERP? - T S * . \ *,4 8/M g 3.7 **YES _ NO A change wnich affects the Security Plan? Y 3.8 YES _ NO _f_ A cnange for which a Licensing Cocument Change has been initiated? 2 Change f 'Ab 3.9 ##YES _ NO A change requiring a new/ revision to a Surviellance Task Sheet Approval form? 3.10 'YES _ NO _,r,. A change affecting the Offsite Dose Calculation Manual (CDCM), the Process Control Program (PCP), or Core Operating Limits Report (COLR).
*Yes requires a procedure revision TCN is not allowed.
**YES reouires Emergency Preparedness or Security Department evaluation.
##Yes Refer to APA-ZZ-00340 for instructions.
- 4. PREPARED BY ff#a M M 6~260N SIGNATURE TITLE DATE
- 5. QUALIFIED REVIEVER AM h -- bJ TITLE 8h~/!h3 DATE SIGNAtg"/
- 6. PRELIMINARY APPROVAL (Prior to implementation) 6.1 SENIOR REACTCR OPERATCR So Mb oS S/WN3 SIGNATURE TITLE DATE' g 7. FINAL APPROVAL (Vithin 14 Days of Implementation) 7.1 APPROVAL AUTHORITY TITLE CATE gg SIGNATURE ph -
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2.1 One Ti.e TCx: YES NO 1 , Effacts ,e from N/4 ,,- N /A _ Z. CHANGE
SUMMARY
2.1 PAGE NLM8ERS AFFECTED SY CHANGE #M ) 2.2 DESCRIPT!0s 0F CHANGE C* of f t C I v#o 2.3 REASON FOR CHANGE b v-Bo 6ff0# s', ,
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- 3. 10CFR 50.55/50.54(P)(Q) APPLICA81LITT - THIS TCM REPRESENT 3: M/
3.1 'YE5 ,._ NO / A change to the facility as described in F5AR7
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3.2 *Y E 5 ,_ NO 2 A change to procecures as described in FSART Q . ~ ISSUED ,k ) 3.3 'YE3 NO g' A test or experiment not described in F5AR wnich could have an 1, et on any , t+ (~~ l structure, systen, ocuipment or comoonent ingportant to safpty? " 3.4 "YE5 NO I A change to the Tecnnical Specifications? -t ' A. PR,05 - 1993 3.5 "YES 3.5 *YE5 ,,,, NO v. A preposed change to any structure.- systee. equipment nNom, oo, en,t? , . NO *" 3.7 **YE3 NO [ A Achange change affecting whten affects thetheenviromant? RERP7 'Q[M.7,1
'X2 N ACCOUNTABE 3.8 **YES _ NO ,,f , A change wnien affects the Security Plan? - WR ,
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YE5 NO .y . A change for wntch a Licensing Docunent Change has been initiated 7 f } 3.10MYES Change i M . No VA change recutring a Surveillance Task Sheet Approval fam?
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3.11 *TES NO 2 A change affecting the Offsite Oose Calculation Manual (00CH), the Process Control. i Program (PCP). or Core Operating Limits Raccrt (COLR).
'Yes answer requires a procedure reviston. TCN is not allowed.
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**YES answer reaut res Emergency Preparecness or Security Department evaluation.
MYes answer - Refer to APA-Z?.-003a0 for instructions. ) 4 PREPARD BY W 2 3 SI RE TITLf DATE
- 5. QUALIFIED REVIEWER M 'M 3
[/ SIGNATultE TITLE CATE ) 5. PRELIMINARY APPROVAL (Prior to Iselement ion) 6.1 5 0!02 REACTCR OPERATCR p 44-n SIGNATUKE TITLE DATE i f
- 7. FINAL APPROVAL (Within 14 Days Imolementation)
; 7.1 APPROVAL AUTHORITY / t4# M I +
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APA-C-00114
OTO-RK-00001 j Revision 2 ) April 1, 1993 l l CALLAWAY PLANT OFF-NORMAL OPERATING PROCEDURE OTO-RK-00001 LOSS OF CONTROL ROOM ALARMS b RESPONSIBLE DEPARTMENT D r%t.// au r PREPARED BY 'N 6 ^ ^ 7 DATE 4/2/93 APPROVED BY /). k/4-<.4 -~., DATE S'/ 2 - 3 f .zv, 3 e %! p 3;Nv 7g 3 1. . ., j
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Mo v.1SSUED DATE ISSUED N-M -N3 74 I gp ; lkPROis 1993 AC000NTABLE ) HOLDy S/ ft This procedure contains the following: i Pages 1 through 11 ) Attachments i 1 through 17 : Tables through l Figures through , )' Appendices through l- Checkoff Lists through
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OTO-RK-00001 4 Rev. 2 LOSS OF CONTROL ROOM ALARMS Y 1.0 PURPOSE AND SCOPE 1.1 This procedure provides guidance in the event of Control Room annunciator alarms ) failure. 2.0 SYMPTOMS 2.1 Spurious actuation of Alarms unrelated to plant status. 2.2 Lack of actuation of expected alarms. 2.3 Plant computer indicating' false information of plant status. 2.4 Failure of annunciator to test. l 2.5 Actuation of SA066X, Engineered Safety l Features (ESP) Status Panel, Alarm l Window 21Q. 3.0 PROBABLE CAUSES 3.1 Failed Field Power Supply in RK cabinets RK045D1, RK045A or RK045B. 3.2 Failed Logic Power Supply (70B-PCD-100) in RK045E1, E2 or E3 3.3 Blown Fuses 3.4 Loss of Supply Power to the RK System. 4.0 AUTOMATIC ACTIONS ) 4.1 None } t. ). ! h
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p OTO-RK-00001 }. Rev. 2 5.0 IMMEDIATE ACTIONS ): 5.1 VERIFY plant is in a stable condition. If not, REFER to the appropriate OFF-NORMAL (OTO) or Emergency (E) procedure. NOTE Annunciator Status and Tracking Procedure ODP-ZZ-00017, Attachment 5 contains a list of the ' annunciators which are . l addressed in the-OFF-NORMAL and Emergency ). procedures with redundant-Control Room indications ' l ~ that are available, if the annunciator has fai)ed. 6.0 SUBSEOUENT ACTIONS ! 6.1 Plant personel should INCREASE the frequency of equipment monitoring and HEIGHTEN awareness of plant status using j the following alternate means: ) a. Control Board Analog Meters L b. Plant Computer
- c. ESF' Status Panels SA066X,Y & Z
- d. Reactor Partial Trip / Block / Permissive Status Panel SB069 l_ e. Miscellaneous Bistable Panel SC066W
- )_ f. Equipment Hand Indicating Switches i g. Local monitoring of equipment and local i L annunciator panels.
l l l l 6.2 CHECK the four Field Power Supplies in , l l RK045D1 for voltage and amp indication. [) l Normal Output Voltage and Amps are 125
- l to 135 VDC and .7 to 1.2 Amps. ,
i l ( l NOTE Two of the Four Field l l Power Supplies in RK045D1 l are required to power the annunciator system. l 6.2.1 CHECK the Logic Power Supply's Power > l Monitor Boards LED indicators for normal l LIT indication, located in RK045E1, l RK045E2 and RK045E3. I
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)-
OTO-RK-00001
;)- Rev. 2 l NOTE There are seven Power ~3 l Monitor Boards, each with l eight LED indicators. Each l LED is labled with the l Logic Power Supply and l Voltage that it is l monitoring. Each LED
[ should be LIT when supply l voltage is available. The [ four output voltages of l each Logic Power Supply l perform the following and j can cause the annunciators
,, l to fail according:
J l l -12 VDC Supply to the Logic Driver l Card; all Annunciators [ powered by that Logic l Power Supply are l inoperable. lGD l [ -6.3 VDC Supply to the Annunciator l Window Light Bulbs; all l Annunciators powered by l that Logic Power Supply
, l are inoperable.
J l l -125 VDC Supply to the Reflash l Cards; only those l Annunciators with reflash l capability powered by that l Logic Power Supply are tb l inoperable. l l -11 VDC Supply to the Light l Flasher, Horn and l Acknowledge pushbutton l relays; the Annunciators O l will still actuate l normally but without l flashing and sounding the l Horn. l s I O
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, OTO-RK-00001 ;
Rev. 2 1 l y l Logic Power Supply (70B-PCD-100 #6 in )- l RK045El is the one exception to the l above information. Only 2 of the 4 l output-voltages are-used. The -12 VDC l supplies the seven Power Monitor Boards l and if it fails, all LED indicators will
- 1 l p g ., gjj g be , DARK and SA066X alarm 21 Q will
) l l actuate. The -11 VDC supplies the-Horn Relays. I j 6.2.2 If the checks performerl in Step 6.2 and l 6.2.1 are normal, then the Optical ' l Isolator Power Supply in RK045A and/or ] l RK045B has failed or the supply to the l Power Monitor Boards has failed. PERFORM l Attachments 15 and 16 for conservatism l which may be' relaxed after I & C has l determined the specific annunciators l affected. ) 6.2.3 NOTIFY I & C and other appropriate l personnel of the abnormal conditions j found and tt initiate corrective l maintenance,on the failed component. l /. . j CAUTION An'.lunciators DQ NOT l necessarily fail to the ! l LIT condition. The ' l failed condition (lit : l or dark) 'is dependent l upon the failed ' l compenent. Do not )_ l assume the only l l affected annunciators I are the ones that are l lit. l l l NOTE Compensatory measures on Page } 17cv 93- of> O l 5 of the Attachments (11thru
- 16) must be initiated within l l one hour.
I i 6.3 If more than 2 Field Power Supplies have l failed, REFER to Attachment 1 andl j perform the compensatory actions. 6.3.1 If a Logic Supply Power failure is suspected, REFER to Attachments 2 > through 16 as required and PERFORM the compensatory actions contained on page 5 of each attachment, j !
OTO-RK-00001 Rev. 2 )- l 6.3.1.1 The Log.ic Power Supply's -125 VDC output l to the Reflash Cards may fail resulting l in " partial failure" and fewer i inoperable annunciators than indicated l on the appropriate attachment l (2 through 14). If this occurs, the
).- l compensatory actions on page 5 SHOULD BE l performed only for the annunciators with l reflash capability as delineated on l Attachment 17 for that failed Logic l Power Supply.
l l 6.3.1.2 The loss of -11 VDC supply from the
) l Logic Power Supplies results in Loss of l the Horn and Flashing capability for the l affected annunciators. Each Logic Power l Supply's - 11 VDC in that cabinet must I be lost for this to occur. Only I heightened awareness of Annunciator
) l Status is required for this failure. I l 6.3.1.3 The loss of -6.3.VDC or -12 VDC results-l in all the annunciators on the l appropriate attachment for that Power , l Supply, to be inoperable. ) l l NOTE The attachments contain l all of the Control Room l annunciators affected by l the failure of each major l component of the RK ) l System, and the minimum l compensatory actions l required to ensure the l plant is in a-safe l condition..The Inoperable l annunciators are ) l highlighted by bold l outline and cross hatched l windows.
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OTO-RK-00001 () Rev. 2 I es l NOTE Failure of three of the 'J l four Field Power Supplies l or the failure of the l Optical Isolator Power l Supplies will also cause l the computer data from l those affected field Ib points to be inoperable. l l Failure of Logic Power l Supplies does not affect j the computer data from the l field points. I C) l l FAILED COMPONENT l LOCATION I ATTACHMENT I l 3 of 4 Field Power Supplies l RK045D1 l 1 l l Logic Power Supply 70B-PCD-100 #1 l RK045El l 2 4D l Logic Power Supply 70B-PCD-100 #2 RK045El 3 l l l Logic Power Supply 70B-PCD-100 #3 l RK045El l 4 l Logic Power Supply 70B-PCD-100 #4 l RK045El l 5 l Logic Power Supply 70B-PCD-100 65 I RK045El ! 6 l Logic Power Supply 70B-PCD-100 #1 l RK045E2 l 7 l Logic Power Supply 70B-PCD-100 #2 l RK045E2 l 8 [) l Logic Power Supply 70B-PCD-100 #3 l RK045E2 l 9 l Logic Power Supply 70B-PCD-100 #4 i RK045E2 i 10 l Logic Power Supply 70B-PCD-100 #1 l RK045E3 l 11 l Logic Power Supply 70B-PCD-100 #2 l RK045E3 l 12 l Logic Power Supply 70B-PCD-100 #3 l RK045E3 l 13 l Logic Power Supply 70B-PCD-100 #4 l RK045E3 l 14 1D l l Optical Isolator Power Supply 70-IDC-1 l RK045A l 15 l Optical Toolator Power Supply 70-IDC-1 i RK045B l 16 l l 1 l Loss of -125 VDC in any Logic Power lRK045E1,2,3l 17 i Supply (use in conjunction with the l l g l appropriate Logic Power Supply l l l attachment) l l 9 O O
i OTO-RK-00001 0 Rev. 2 .j i 1 I l () l CAUTION A " partially failed" l Logic Power Supply l should not be l considered failed. (See l Step 6.3.1.1 and l 6.3.1.2) O' 6.4 REFER to EIP-ZZ-00101, CLASSIFICATION OF EMERGENCIES, Group 3 Safety System Functions. 6.4.1 On failure of three or more Field Power C)- Supplies, (loss of all annunciators) an Alert MUST be declared. OR 6.4.2 If all thirteen Logic Power Supplies C) have failed (loss of all annunciators) an Alert MUST be declared. OR 6.4.3 If any other combination of power supplies (including Optical Isolators) C) have failed, and the minimum compensatory actions of the appropriate attachment (s) cannot be maintained, DECLARATION of an Alert SHOULD be considered due to reduced' safety. assessment capability. NOTE Plant transient is defined as: (for use in identifying' emergency ; classification) ) i O a. Change in Reactor power greater than 1 5%/HR
- b. RCS temperature deviation of greater than i 30 F from Tref.
- c. PZR pressure deviation of greater than 1
+ 15 PSIG from 2235 PSIG. !
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i OTO-RK-00001 Rev. 2 l l 6.5 ENSURE Tech Spec required plant , j monitoring is initiated for the failure l of any of the following alarms. I
- l ALARM NUMBER l ALARM NAME I REQUIRED SURVEILLANCE I I i l 65D l T Ref/T Auct HI ] OSP-ZZ-00001 Att. 5 I I I p l 78B l PR Upper Flux Deviation l OSP-SE-00003 I I I l 78C l PR Lower Flux Deviation l OSP-SE-00003
! I I l 79C l RPI Dev or PR Tilt l OSP-SE-00003 h l l l OSP-ZZ-00001 Att. 4 I I i l 79D l AQ Out of Band l OSP-SE-00002 I l l l 80C l RPI Rod Dev l OSP-ZZ-00001 Att. 4 l l l l 81C l Rod Bank LoLo Limit l OSP-ZZ-00001 Att. 3 6.5.1 If any SI Accumulator annunciator window for pressure or level is inoperable (43 through 46 B or C) RECORD the
! pressure and level for the affected SI ) Accumulator at least once per hour in the URO narrataive log. USE computer points or MCB analog meters. 6.6 DETERMINE from the attachments, what additional monitoring of plant equipment ) is desired. CONTACT appropriate personnel as needed to monitor equipment locally. 6.7 If Plant Startup or Plant Load Changes
- are in progress consideration should be
) given to the extent of annunciator failure and ability to ensure plar.t is in a safe condition. Limit load changes to less than 5%/HR and STOP plant startup operations until the-l annunciators have been repaired. I 1
OTO-RK-00001 )- Rev. 2 6.8 The power supplies for the (RK) y Annunciator System are as follows, and the attachments to refer to upon loss of power are listed: I l l COMPONENT l l REFER TO l PWR SUPPLY l LOCATION COMPONENTS I ATTACHMENTS. ) l I l PK5216 l RK045D1 l Field Power Supplies'#1 l 1 If 3 of l l l and 2 l 4 Field l l l l PWR Supplies l l l l have failed l l l l- . l PK5119 l RK045D1 l Field Power Supplies #3 l 1 If 3 of l l l and 4 14 Field l l l l PWR Supplies. l l l l have' failed I I I I l PK5202 l RK045El l SX Logic Power Supplies 2-6 ) l lSce Note l 1X Horn Relay Power Supply l l , l lBelow l 70B-PCD-100 #1,2,3,4,5 & 6 -l 1 l- 1 i l PK5216 l RK045E2 l 4X Logic Power Suppliei l 7-10 l l l 708-PCD-100 #1,2,3 &4 l 1 I I I ) l PK5116 l RK045E3 l 4X Logic Power Supplies l 11-14 l l l 70B-PCD-100 #1,2,3,4 i I i l i l PK5118 l RK045A l Optical Isolator Power l 13 l l l Supply 70-IDC-1 l l l l Seperation Group I l ) l l l l l PK5222 l RK045B l Optical Isolator Power l 16 l l l Supply 70-IDC-1 l l l l (Seperation Group II) l I i ). l NOTE Logic Power Supply l (70B-PCD-100 #6) in j l RK045El is for Horn Relay H l Power and the Power l Monitor Boards. If it )~ l should malfunction, no l l operability concern j exists, however increased ; j awareness of' annunciator j l status would be l 1 appropriate. l )- I i [ u i
OTO-RK-00001 g Rev. 2 NOTE The 120 VAC Power is supplied to the RK O Cabinets only for cabinet receptacles and cooling fans. The power source is from the 42 circuit distribution panels on PG19G and PG20G. 120VAC
# Power for the computer multiplexer in RK045D2 is PQ05 breaker 10.
6.9 MARK the MCB analog meters using a grease pencil to help identify any adverse trends. O 6.10 BUILD computer group displays or call up existing group displays to aid in monitoring affect plant equipment. l NOTE Pages 1 through 4 of 3 l Attachments 2 through 16 l are developed by the l Drafting Department using l the CAD System. Any j changes (ie. TCNs, CMPs, l Revs etc.) should be 9 l completed by the Drafting l Department.
7.0 REFERENCES
7.1 J-108-00349 7.2 J-108-00102 7.3 J-108-00106 7.4 J-108-00107 7.5 J-108-00108 7.6 J-108-00109 7.7 OP-J-26005
- O 7.8 E-23RK001 O
i _lo_ 3 I
1 OTO-RK-00001 * } Rev. 2 4-7.9 EIP-ZZ-00101 7.10 OSP-SE-00003 7.11 OSP-SE-00002 7.12 OSP-ZZ-00001 k 7.13 ODP-ZZ-00017 - 7.14 E-23RJ07 ) ) ) ' ) h
OTO-RK-00001 () Rev 2 Compensatory Actions for Loss of Field Power Supplies 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as of ten as possible but in all cases at a minimum of once per hour.
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3.) Reactor Operators should monitor equipment / parameters continuously. 4.) Per Step 6.4.1 of this procedure, an ALERT must be declared due to reduced safety assessment capability. ') 5.) Computer data from the affect field points is not valid. I I i l Work Area l Equipment / Parameter l
) l l l l Control Room l Boric Acid Tank Levels, VCT Press / Level, l l L) [ RMCS, Ltdn & Chrg Flows & Temp, P:r Level / Pressure / Heaters , l l 2) l RCS Temperature, RCP Parameters, SI Accumulators, l l 3) l RWST Level, SB069 Bistable Panel, SFP Level, Cond. Vacuum, l l 4) l Steam Seals, Cond. Pmp. Disch. Press, CST Level. [
C) l 5) l l l l CMPTR Mux Group Display, SI Accumulators, l l l SB069 Bistable Panel, CCW System, CTMT S ump s , Emerg D/G Day l l l 6 Storage Tank LVLS, CVCS LTDN Pressure ( l } ! l l CT B/D & Bypass Flow, SB069 Bistable Panel, Nuclear Inst, j [] l l Per heaters, RCP Parameters, RM-ll, Area Rad Monitors, l l l Turbine Load for Cire Pmp Setback, CCW System, DRPI l l l 1 l l Intake Flow, Cooling Tower Level and B/D Flow, Turbine Load,l l l CMPTR Group Display N2 Accum Pressure l l l Reactor Coolant Pump Temoeratures l C) I I I l Secondary l LP and HP FW HTR Levels, MSDT/lst & 2nd STG RHDT valve l l l positions, Main Turbine L.O. and EHC, Main Generator Stator l l l Cooling /H2 Local Panels, CLCW Pumps and System Flow. l l l l l l ESF SWGR Rooms Temperature, NK Batteries, NN Inverters, j [) l l Instrument Air Compressors, Central Chillers, Main l l l Feed Pumps, Main Generator EHC Room, Computer Room Temp. l 1 I I l l PK, NK and Emerg Diesel Local Panels, NN Inverters. l-1 I I l l PK Buses, Instrument Air Dryers, HP and LP FW Heaters [ gp l l LVL/ Valve pos, Isophase Bus Cooling, Main Generator Stator l g l __, I Coolinn / H2 Local Panel. CLCW pumps and System Flow. l 1 of 2 Attachment 1 O
OTO-RK-00001. j Rev 2 I I i l Work Area l Equipment / Parameter l l 1 I i ) I I l Inside l' Unit Aux and Main Transformers l ' l 1 . l-l l Start Up, Main, Unit Aux and ESF Transformers l 1 i 'l l l ESF, Unit Aux, and Station Service Transformers l , l l NG05E and NG06E MCC's, NG07;and NG08 Load Centers l l l l l l UHS Level. UHS Freeze Protection l; I i 'l l Primary l SFP Cooling and Cleanup l-
'l 1 1 l l CVCS Heat Trace l
) l l l ' l l CVCS HT Trace, Rod Control (if rod motion required), l l 1 MG Sets. Rad Mon HT Trace Panel l l 1 I l~0utside l Cire & Service, Water' Treatment and Sludge bisposal l 1 1 I )- l l Switchyard l l 1 l
- 1) Monitor BOP ESFAS & LSELS ATI once every 30 minutes.
- 2) Inform Hot Lab that C0/CO2 Monitor will not alarm in the Control Room.
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- 3) Notify Chemistry that Sewage Misc. Trouble and Process Sample Trouble vill not alarm in tho' Control Room. '
- 4) Monitor LSELS ATI and SSPS General Warning once every 30 minutes,
) 5) Monitor RCP Vibrations, Loose Parts Monitor, ATWS & Seismic once every 30 minutes. i i ) l l )' -l 1 1 l 1 ). i t 2 of 2 Attachment-1 1 i--. I ). J
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U U Uf. U U .U - U .U~ .U- _(I U " OTO-RK-00001 Rev 2 Compensatory Actions for Loss of logic Power Supply 70B-PCD-100 #1 FK045El 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current-plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I I l Work Area l Equipment / Parameter l l 1 1 I I I l Control Room l Intake parameters, Cooling Tower Level & Disch/ Blowdown Flow, I l
- l Turbine load for Circ Pap setback, l l .l- Service Utr Pump Status l l-. I l 1 1 I l Outside l Switchyard, Cire and-Service !
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OTO-RK-00001' Rev 2 Compens a to ry Actions for Loss of I.onic Power Supplv 70B-PCD-100 #2 RK045El 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour. I 3 .' ) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal available, or due to computer
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I- ! I I I l Work Area. l Equipment / Parameter l 1 1 I I I I l l Control Room 'l .PA & NB Bus. Voltage l I I
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5 of 5 Attachment 3 _ _ _ _ _ _ - - _________________m__ - _ - - - - . - _ . _ _ _ _ _ _ _ _ _- .__- -- - _. -_ . u. . . . . - _ _..a -
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OTO-RK-00001 Rev 2 Compensatory Actions for Loss of Lonic Power Supply 708.PCD-100 #3 RK045El 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I I l Uock Area l Equipment / Parameter l
- i. I I I I I l Control Room l Pzr lleaters l l
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- Monitor LSELS ATI once every 30 minutes.
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v -w .y v C' y_ v- v.. v- v- u - r- , 1 OTO-RK-00001 Rev 2 Compensatorv Actions for loss of Lor.ic Power Supply 70B-PCP-100 #4 RK045El 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this. attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of 'once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. , 4.) If' monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I I
-l Work Area l Equipment / Parameter l I I I I I I l Control Room l PZR UVL and Press, l l- ** l 'CVCS parameters, VCT level / press, Chg and Ltdn Flow / Temp, l ;
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OTO-RK-00001 Rev 2 Compensatory Actions for Loss of Lonic Power Supply 70B-PCD-100 #5 RK045El 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as of ten as possible
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-l i I I i . I l Control Poom l PZR Level / Pressure and Heaters l
- l l CVCS Parameters; VCT Level / press, RMCS, Ltdn and l
[ .. l Chg Flow / Temp, SI Accumulaator 'D' l 1 ~l l' I l i 1 l Primary l CVCS Heat Trace [ l i I 5 of 5 - Attachment 6 1 _ . - _ . _ - _ _ . . - _ _. . . _ _ _ - - __ ..___________..._._..._x. -._s_ . . _ .._ ; ._ _ , -. _ _
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1 OTO-RK-00001-Rev 2 . Compensatory Actions for Loss of Log.c Power Supply 70B-PCD-100 #1 RK045E2 [ r 1.) The table'below contains the minimum required equipment / parameters that should be 7 , monitored during this power supply loss. More actions can be taken if a review of - t this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases.at a minimum of once per hour. 3.) Reactor Operators should monitor. equipment / parameters continuously. , 4 l 4.) If monitoring cannot be maintained with personal available, or due to computer ; unavailability, declaration of an ALERT should be considered due to , reduced safety assessment capability. 1 I I l Work Area l Equipment / Parameter [ l I I I . I I l Control Room l CCW Parameters; Flow / Pump Status, l j'*# l RM-II, Area Rad Monitors, SFP Level, l l l RCS Temperature l ' l- l 1 l Primary l l 1 -l C0/CO2 Monitor, SFP Cooling and Cleanup l 4 I I l l Secondary l ESF Swgr Room Temperature l 4 l 'I l i l ! ! l'Inside l UHS. Level and Freeze Protection l 1 l' I
- Monitor LSELS ATI once every 30 minutes.
# Inform Hot Lab that C0/C02 Monitor will not alarm in the Control Room.
_ 5 of 5 -Attachment 7
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_ - - - .; v. v- . f -- % . y- v- -v- y OTO-RK-00001 Rev 2 Compensatory Actions for less of Logic Power ~ Supply 70B-PCD-100 #2 RK045E2
-1.)- The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions.
2.) Equipment Operators should monitor equipment /paramet .rs as often as possible but'in all' cases at a minimum of once per hour. 3.) : Reactor Operators should monitor equipment / parameters continuously.
~4.). -If monitoring cannot be maintained with personal available, or due to computer unavailability, ' declaration of an ALERT should be considered due to reduced safety assessment capability.
l - 1 I
.l Work Area l Equipment / Parameter l I I I I I I l Control Room. [ RCP Temperatures and Seal Parameters, CCU Flow / Temp, l l- l RM-ll, Area Rad Monitors, DRPI, SB069 Bistable Panel, l l l Tave-Tref deviation. Group Display Computer Mux Status l l 1 l l Primary l Rad Mon IIeat Trace' Panel l l l- Rod Drive MG sets l l I 1 s- 11 1 - l l Secondary l Computer Rm Temp l 1 I I
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y--- g---g--------- .- -------y-- -----g - OTO-RK-00001 Rev 2 Compedsatory Actions for Loss of Lonic Power Supply 70B-PCD-100 #3 RK045E2 ' ~ ' 1.) The table below contains the minimum required equipment / parameters that should be i monitored during this power supply loss. More actions can be taken if a review of ~ this attachment, along with current plant 7tatus, watcants such actions. 2.) Equipment Operators should monitor eauipment/ parameters as often as possible but in all cases at a minimum of once per hour.
.3.)' Reactor Operators should monitor equipment / parameters cor,;inuously.
4.) If monitoring cannot be maintained with-personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I i l l Work Area l Equipment / Parameter ~l ., I I I 1 l I 3 l Control Room l CVCS Charging Flow and VCT Press, l l,
- l $1 Accumulators, Nuclear Instruments, DRPI l _
l l RCP temp and Seal Parameters l , I I I l Primary l Seal Inj ./RC Filter 'D/P l l 1 1
'* Monitor RCP Vibrations, Loose Parts Monitor and SSPS General Warning once every 30 minutes. l t
5 of 5 Attachment 9 a .. _ . _ _ _ _
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- d' O- -O- O- O O O- O O. O- LO OTO-RK-00001' Rev 2 Compensatory Actions' for Loss of Lotic Power Supply 70B-PCD-100 #4 RK045E2 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions.
2.) Equipment Operators should monitor equipment / parameters as often as possible but-in all cases at a minimum of once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with.personel available, or due~to computer unavailability, declaration of an' ALERT should be considered due to reduced safety assessment capability. I I I l Work Area l Equipment / Parameter l 1 I I I I i l Control Room l PZR lleaters, Area Rad Monitors, l l
- l SI Accumulator 'D', DRPI, l' l l RCP Temperatures. SB069 Bistable Panel l t I i l~ Primary l CVCS Ileat Trace l l l Rod Drive MG sets l l t i I I l-l Inside l UHS Freeze Protection l l I I
- Monitor ATWS Panel once every 30 minutes.
15 of 5 Attachment 10
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_- - .y- - - v .- m .m - .v OTO-RK-00001 Rev 2 Compensatory Actions for Loss of Loric Power Sunniv 70B-PCD-100 #1 RK045E3 1.) The. table below contains the minimum required equipment / parameters that should be monitored during this-power supply loss. More actions can be taken if a review of this attachment, along with current plant. status, warrants such actions. 2.)' Equipment Operators should monitor equipment / parameters as often as possible but in al1 ~ case; at a minimum of once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be' maintained with personal available, or'due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I I l Work Area l Equipment / Parameter l l I l 1 I . I l Control' Room l . Emergency D/G Day and Storage Tank Levels, l l l Condensate Pumps Bearing Temperatures, l l l S/G Level s . ' CST Level l l 1 . l l- l Air Compressors & Dryers, Central Chillers, l-l Secondary- 'l Heater Drain Tank Dump Valve position. l l l HP and LP IITR Levels, MSDT/lst STG/2nd STG l [. l Valve. positions l 1 1 I 5 of'S -Attachment 11 _m._
_ ~ OTO-RK- J01 Rev. 2 LOGIC POWER SUPPLY 700-PCO 800 #2 RH045E3 1 2 3 4 5 6 7 8 9 to il 12 13 e.... ..= w .. n. A . c.,
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_- - ~ ~ - ~ _ .. ., .. .. OTO-RK :0001E REV. 2 LOGIC POWER SUPPLY 70B-PCD-LOO #2 RKO45E3 70 71 72 73 74 75 76 77 78 79 80 81 82 83
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y . OTO-RK-00001 Rev 2 Compensatory Actions for Loss of Logic Power Supply 70B-PCD-100 #2 RK045E3 1.) The table below contains the minimum required equipment / parameters that should be j monitored during this power supply loss. More actions can be taken if a review of j this attachment, along with current plant status, warrants such actions. lj i 2.) Equipment-Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour.
- 3.) Reactor Operators should monitor equipment / parameters continuously.
4.) If monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I. I I l Work Area [ Equipment / Parameter l I I I o l I . 1 i ! l Control Room l B Emerg D/G Day Tank Lvl, Group Display N2 Accum Tank Press,l _j l*# l Condensate Pump; Bearing Temp, l ] l I S/G Levels. Demin Tk Lvl l l l l l Primary I j l .
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'l .
I I l Inside i Uni r Aux X FMR . Main XFMR l
- Monitor Seismic System once every 30 minutes.
# Notify ~ Chemistry that Process Sample-Trouble will not alaim in Control Room.
5 of-5 -Attachment 12 l i>_.LL~_-_--_____-----__ -
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Page 2 of 5 ATTACHMENT 13 i
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OTO-RK-00001' Rev 2-Compensatory Actions for Loss of Loeic Power Supply 70B-PCD-100 #3 RK045E3 1.) The table below contains the minimum required equipment / parameters that shr.uld be monitored during this power supply loss. More actions can be taken if a review of ' this attachment,-along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once por hour. 3.) . Reactor 0.erators 1 should monitor equipment / parameters coatinuously.
- 4) If' monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability.
I I I l Work Area l Equipment / Parameter l 1 I I >
.I i. I l Control Room l Condenser Vacuum l ,
'l
- l Computer Display for N2 Accum. Press l l 1 1 1_ .
I i l Secondary. l Main Turbine Lube Oil, Isophase Bus System, l l l EllC System. A and B MFP l
- Monitor RCP Vibrations once every 30 minutes. .
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OTO-RK-00001 Rev 2 Compensatory Actions for Loss of ; Logic Power Supply 70B-PCD-100 #4 RK045E3 [ The table below contains the minimum required equipment / parameters that should he
~
1.) monitored during this power supply loss. More actions can be taken 2 a review of 1 this attachment, along with current plant statys, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour. , 4 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal available, or due to computer : unavailability, declaration of an ALIRT should be considered due to ;
- reduced safety assessment capability, l~ l l l l Work Area l Equipment / Parameter l 1 I i 1
-l I i ,
- l. Control Room l Area Rad Monitors, l t
.1
- l Emergency Diesel Gen Day Tank Levels, l l l Turbine Vibration. Steam Seal System- l 1 1 I i J. l: Main Turbine Lube Oil and EllC, l l Secondary l -A and B MFP's, PK. Batteries, l l l Main Generator Stator and 112 Tecal Ann. Panels l ~t l l I l Inside l . Unit Aux and Main XFMR l t l 1 l-
- Monitor BOP ESEAS ATI once every 30 minutes.
+
- 'S of 5' . Attachment 14
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y - y -- -y y y u y y_ - -y -- g OTO-RK-00001 Rev 2 Compensatory Actions for Loss of optical Isolator Power Fupply 7C-IDC-1 RK045A 1.) The table'below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible but in all cases at a minimum of once per hour. 3.) Reactor Operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I i l Work Area j Equipment / Parameter l 1 1 I l I i l Control Room l 'A' PZR-B/U Htrs, 'A' CCP Status, l-l
- l 'A' Train CCW Pump Status and Flow l l I I I i l l Primary i 'A' Train SFP Cooline l 1 1 I l_ Secondary. -l 'A' Emerg Diesel, NG01 and NG03 Load Centers, j
.I I I l- . I I
~l Inside l NG05E'MCC -NG07 Load Center l
. I I i
- Monitor . ' A* Train LSELS ATI once every 30 minutes.
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OTO-R. .10'01 REV. 2 OPTICAL ISOLATOR POWER SUPPLY 70-IDC-l RKO458 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 A W m 2 N - /.
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-9 r d RK020 ESFAS ATTACHMENT 16 Page 2 of 5 -
..OTO-RK .s001a REV. 2 OPTICAL ISOLATOR PCWER SUPPLY 70-IDC-8 RK045B 70 71 72 73 74 75 76 77 78 79 80 81 82 83
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OTO-RK-00001 Rev 2 Compensatory Actions for Loss of Optical Isolator Power Supply 70-IDC-1 RK045B 1.) The table below contains the minimum required equipment / parameters that should be monitored during this power supply loss. More actions can be taken if a review of this attachment, along with current plant status, warrants such actions. 2.) Equipment Operators should monitor equipment / parameters as often as possible
-but in all cases at a minimum of once per hour.
3.) Reactor-operators should monitor equipment / parameters continuously. 4.) If monitoring cannot be maintained with personal- available, or due to computer unavailability, declaration of an ALERT should be considered due to reduced safety assessment capability. I I I l Work Area l Equipment / Parameter l 1 I I I I I l Control Room l 'B' PZR B/U liTRS, ' B' CCP Sta tus , l l *. l 'B' Train CCW Pump Status and Flow l l 1 1
-l- l 1 l Primary l 'B' Train SFP Cooline Pump l 1 i .
l l Secondary _ l 'B* Emerg Diesel, NG02 and NG04 Load Centers. l 1 I I I i . l l Inside .l. NG06E HCC, NC08. Load Center ~l 1 I I
- Monitor B' Train: LSELS ATI once every- 30 minutes.
. 5 of 5 Attachment 16 l
. - . _ .- _ . ~ . ..
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OTO-RK-00001 Rev. 2 ANNUNCIATORS WITII REFLASH CAPABILITIES 1). Use this attachment in conjunction with the appropriate Logic Power
- Supply attachment if only the -125 VDC has failed to determine which annunciator have reflash capability and are affected by the failure.
- 2) Annunciators that have reflash capabilities are highlighted by bold outline and cross hatched windows.
- 3) Reflash windows have multiple inputs from the field into the RK cabinets. A window with reflash capabilities will re-alarm when a new l alarm occurs (with an existing alarm present) from one of the other inputs.
- 4) Reflash of a window that is a common alarm window for a local annunciator panel (i.e., Aux Steam Sys. Trouble) is dependent on the reflash capabilities of the individual local annunciator panels. The local annunciator panel may require local acknowledgement to allow a different local alarm input to bring in the common MCB annunciator.
1 I 1 Page 1 of 5 Attachment 17 a - _ __ 1 _' __ ______--m___m__
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___, _y__ _ _ _ _ _ . _ . . _ _ _ _ . g g I. OTO-RK-00001 Rev. 2 AffAJNCI ATORS WITH REFLASH CAPASILITIES I 2 3 4 5 6 7 8 9 to 8I 12 13
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RKol6 STATION ELECTRIC . Page 2 of 5 f.~r!.CDfE K 17
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5 r RK020 ESFAS-Page 3 of 5 ATTACIMENT 17
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OTO-RK-00001 Rev.'2 ANNltJCI ATORS WITH REFLASH CAPABILITIES 70 71 72 73 74 75 76 77 78 79 80 81 82 83
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