ML20091K941
| ML20091K941 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/01/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TP-1-A-1350-25A, NUDOCS 8406070253 | |
| Download: ML20091K941 (80) | |
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T ' ~.:,..a ' ^ a6 Form 34811 (7-81) -'"'*w (Formerly SPD-1003-2) DUKE POWER COMPANY (1) ID No: W 'i ' /* r T O 2 F /- i PROCEDURE MAJOR CHANGE ChangeJio: ~7 PROCESS RECORD Permanent'/ Restricted To (2) STATION: / ~4.. *.04 ~ (3) PROCEDURE TITLE: h A // - /^ u s. u,7 A.,,o [./A: 2.3-7 T.n n./ [1 o 7 7 ft:7.g V/1--? u, r: ,/ A """' / (4) SECTION(S) 0F PROCEDURE AFFECTED: / 3. O (5) DESCRIPTION OF CHANGE: (Attach additional pages, if,necessary.) ~ , t. > e u / r "^,,. 5 ;;{ u T ,;.,;,4,' ~c > frw tian ~ iv,~0 a ~ fu /.,3 4,,,c i?.j S cjf.uv[Oji.,yp,.g;.Op" L,y4.2 b,,n (r,r p,1: u (6) REASON FOR CHANGE: ,,, -.,. x. 7,_: : r. ~,@ 1,>m<, % < > = r. r /m* m ' ~ - ' : 2,
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[ 66 (8) SAFETY EVALUATION This change: Yes No Represents a change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR? Yes No Requires a change to the station Technical Specifications? Yes No Involves an unreviewed safety question? If the answer to any of the above is "Yes", attach a detailed explanation. As appropriate attach a completed'" Nuclear Safety Evaluation Check List" form. By: I Date: 3-/ O'N (9) REVIEWED BY: / /v,,.cDATE: 7-19 94 Cross-Disciplinary Review By: N/R: / (10) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO).Date: By: Date: (11) APPROVED BY:
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r-~ y. .......o_. ,s. Form 34811 (7 81) q (Formerly SPD 1003-2) DUKE POWER COMPANY (1) ID No: ' ~/ i:/ -E !? U PROCEDURE MAJOR CHANGE ChangeJo: PROCESS RECORD Pefianen't/ Restricted To (2) STATION: / A, ;.,,:. ' 2 -(3) PROCEDURE TITLE: D /'-, Id 12e R u, A O [/;An)d X O.tv I,2/rA L' A', v. ? b.? (4) SECTION(S) 0F PROCEDURE AFFECTED: IN, I. / 2./~ !'.6 O -(5) DESCRIPTION OF CHANGE: (Attach additional pages, if necessary.) $.( t-" /^~/7-(fp ; n 6' -(6) REASON FOR CHANGE: % r.~h - ce? i-Y I' l ". (7) PREPARED BY: DATE: (8) SAFETY EVALUATION This change: Yes No s' Represents a change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR? Yes No Requires a change to the station Technical Specifications? Yes No Involves an unreviewed safety question? If the answer to any of the above is "Yes", attach a detailed explanation. As appropriate attach a completed " Nuclear Safety Evaluation Check List" form. s.'. 1 By: h /[ lm / Date: blf'N Y ~/ /,\\s ,.f' 7 ', 2 ':: ".. c. (9) REVIEWED BY: M ;/ ' AW DATE: Cross-Disciplinary Review By: N/R: I/ ' / (10) TEMPORARY APPROVAL (IF HECESSARY): By: (SRO).Date: By: Date: (11) APPROVED BY: \\. * # / DATE: / .'V + o j (12) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: (13) Page 1 of Rev 14 9/20/77
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ryT- ~, 4 Form 34811 (7-81) 6 ,N (Formerly SPD-1003-2) .s DUKE POWER COMPANY '(1) ID No: 7 "/ i i' r JJ/ZM. t PROCEDURE MAJOR CHANGE Change.No: ~ PROCESS RECORD Pe'rmanenl/ Restricted To (2). STATION: '*AcM Mki/A bcTM bA7Mu ihMM.n (3) PROCEDURE TITLE: _ {g. (4) -SECTION(S).0F PROCEDURE AFFECTED: /r M, f'T ~(5) DESCRIPTION OF CHANGE: (Attach additional pages, if necessary.) ~' ' ' - ' ',. ' i. :.. e. (6) REASON FOR CHANGE: / (7) PREPARED BY: DATE: ' ~ '
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(8) SAFETY EVALUATION This change: Yes No Represents a change to the station or procedures as described in the FSAR, or a test or experiment.not described in the FSAR7 Yes No Requires a change to the station Technical Specifications? Yes No v Involves an unreviewed safety question? If the answer to any of the above is "Yes", attach a detailed explanation. As appropriate attach a completed " Nuclear Safety Evaluation Check List" form. N. ")-lb 'b Y By: %i Date: a.;u ' M,,7./ 6/4Iev,% (9) REVIEWED BY: DATE: r r5 #t/ .i Cross-Disciplinary Review By: N/R: /b (10) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO).Date: By: Date: DATE: . : '- /*V (11) APPROVED BY: 'tv- / (12) MISCELLANEOUS' Revieued/ Approved By: Date: Reviewed / Approved By: Date: .e (13) Page 1 of ~~ Rev 14 9/20/77
O 8 (6-82) ( ', 7*:!,;frt l'l'G'/G? ' cly SPD 1003 2A ~ ID No: DUKE POWER COMPANY PROCEDURE MAJOR CHANGE Change No' PROCESS RECORD CONTINUATION FORM Page_ of ~~ h5(l' ff A) {f- ~&!i 0 h l lM hJC t ?>..C. '" k. 0 C $' O! ,0 / ' b'2$O / L t-LT !\\/ h. D o /$w.,a Dev,,c- ~ 'nd li Imc/it, i%~;&g " twag C,, ~.e ~~ llIf; Y '. ;'
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...l w. .a ..,,,. ~.,,....,.......... _ _ o :.,.' c *. :; Form 34811 (7 81) p q (Formerly SPD-1003-2) ~ DUKE POWER COMPANY (l') ID No: V!'/d!/25U? #', PROCEDURE MAJOR CHANGE Change No: '4 PROCESS RECORD V ~t/ Restricted To Permanen .(2) STATIONi ( ,r G 'e d 6/'NCt fat o b'/ O. 3:'? '7, /v/ ' (14'-M/ Ar,I (3)' PROCEDURE TITLE: ! l-7 / E p .....S r ~' ; - ~ (4) SECTION(S) 0F' PROCEDURE AFFECTED: '0 be i /. ( - (5) DESCRIPTION OF. CHANGE: (Attach additional pages, if necessary.) ?,..;' * " ?c & *~,,;- \\ C .(6) REASON FOR CHANGE: G~ g,,c '.it a < c f. Ll? y /.up ~7 t' h '/n ~ fr ' MU n' 3-
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,a< (8) SAFETY EVALUATION This change: Yes No Represents a change to the station or procedures as described in the FSAR, or a test or experiment.not described in the FSAR7 Yes No Requires a change to the station Technical Specifications? Yes No. Involves an unreviewed safety question? If the anstTer to any of the above is "Yes", attach a detailed explanation. As appropriate a'ttach a completed " Nuclear Safety Evaluation Check List" form. W/ Date: 3Db By: \\ ' (9) REVIEk BY: // I A,<,DATE: 3-2 3-8t/ / Cross-Disciplinary Review By: N/R: ??- (10) TEMPORARY APPROVAL. (IF NECESSARY): t<[ h y."..; b (SRO) Date: ?> - 2 E 5 By: By: 4 m +f Date: r - n (11) APPROVED BY: DATE: /, t - (12) dl5CELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: (13) Page 1 of Rev 14 9/20/77
...e +. Form, 34895 (6-82) /~' O Formerly SPD 1003 2A q,/ s) DUKE POWER COMPANY ID No: 5, ~ PROCEDURE MAJOR CHANGE 4 PROCESS RECORD CONTINUATION FORM ""E" S of Page u /d !A Tts,;nuJ if- (,,,j,s.cq ; ' Ch /h2d SW5 8. lb Av0 $< D WI!> itvCW6UOL%T' I/L1,RCMnv /8 (mcu.)s ' /.=.=.1= s 3 (c. b sccws i2.t mnvcvi222 * -llw nu,nevz e M J.55 L M 5 F -lins r-2 tij il*R VC 6 y."rT3 =,J. i 5 ?.' ? t ~.O A J 2iJi.% ta',1*a~ze ,i,. m a c:. s _I - ) - TS I ~I .l St-tn as I ?. t &,n,../I ?. 2 krW f 3binn n-v! /" W-~; /. tM e I- $ %,9 h 2 7 '/ /UW b N ,;. 5 s r x A.y, z ..N.6. n,vi w,~~. y i1-o u, n,4 ' \\ i Q 'a l CL c.5. /.ri bC n4G C thAicM W'7:mW SfhnI." 25 An%T*01l'vv7 % tOAli.vG $ I /// Al/n CitG Ji? { /*-? .b#
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T e e,j ' . Form 34811 (7-81) '] (Formerly SPD 1003-2) DUKE POWER COMPANY (1) ID No: [J// M !C M PROCEDURE MAJOR CHANGE Chan.geJo: 5 PROCESS RECORD P g nent/ Restricted To (2) STATION: ( *,hw 9 (3) PROCEDURE TITLE: ' D. th // dt A a # /h O b/b'7 /d 761 h AJ htt-MV /H avAt. Q --- ~ ~ ~ ~ ~(4) ~SECTION(S)? 0F PR6CEDis'RE TJFECTED:' UC ~ ' - ~ ~ ~ ~ ~ ~ ' ~~ (5) DESCRIPTION OF CHANGE: (Attach additional pages,'if n'ecessary.) ~ f-T l w e'G f,..*L V *i (6) REASON FOR CHANGE: [-r,Lcf:- ;, -1".'. ~ (7) PREPARED BY: 'l DATE: I'E ~ (8) SAFETY EVALUATION This change: Yes No Represents a change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR? Yes No Requires a change to the station Technical Specifications? Yes No Involves an unreviewed safety question? If the answer to any of the above is "Yes", attach a detailed explanation. As appropriate attach a completed " Nuclear Safety Evaluation Check List" form. By: I / l' '. 'w' Date: 3 - O-M / ^ s')3 ^I DATE: 3/77 (9) REVIEWED BY: ,,g !s l l Cross-Disciplinary Review By: N/R: (10) TEMPORARY APPROVAL (IF NECESSARY): / /' By: (SRO).Date: -' By : .Date: a e v .' s / i (11) APPROVED BY: DATE: / ~ ' / - I (12) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: (13) Page 1 of 9 Rev 14 9/20/77
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F 2. ...:...r..a........ ~w' ' . Form 34811 - (7 81)' -A A (Formerly SPD-1003 2) ' DUKE POWER COMPANY '(1)' ID No:' TS!. /1/w T/ /C C '- / PROCEDURE MAJOR CHANGE Change No
- 2 PROCESS RECORD PersanEit/ Restricted To
~ (2) l STATION: L A~.'.. w'. A (3)- PROCEDURE ~ TITLE: D/b /4 l$t hv r ,4w [CM d 7 fen:wj (cmc 8-Wh. -If57 -(4) 'SECTION(S) 0F PROCEDURE AFFECTED: / R, C / A 6.0 (5) DESCRIPTION OF CHANGE: (Attach additional lpages, if necessary.) hty g-9c,-@ Sn:-if ~ (6). REASON FOR CHANGE: 0>,..:..? , - ~ ye - <... r DATE: Y 'b~
- (7)- PREPARED BY:
~ -(8)' SAFETY EVALUATION. / -This change: Yes Fo X Represents a change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR? -Yes No Requires'a change to the station Technical Specifications? Yes No Involves an unreviewed safety question? If~the answer to any of the above is "Yes", attach a detailed explanation. As appropriate attach a completed " Nuclear Safety Evaluation Check List form. \\ .,.d Date: 3 Ib- @ By: ?!F'E ' $ l.), "'.,, v.4 DATE: (9) REVI D BY: / i ,,Ji?l . Cross-Disciplinary' Review By: N/R: r F-(10) TEMPORARY APPROVAL (IF NECESSARY): / By: (SRO).Date: By: Date: DATE: /' ' / 'l (11)' APPROVED BY: (12) MISCELLANEOUS:- Reviewed / Approved By: Date: Reviewed / Approved By: Date: (13) Page 1 of Rev 14 9/20/77
~. .r. e f.. Form 348951682r f' I - ~ N ~ ' Formerly SPD 1003 + 2A - ('~' ~- s
- ///a }/3 R/'Wi.
s DUKE POWER' COMPANY ID No: PROCEDURE MAJOR. CHANGE 1 PROCESS RECORD CONTINUATION FORM Change No: m ~f 0 -t Page o m Y ccessur; Cin.w = F bid 1c CueesA 'I3.3 vivert Aux komu %st m l'c." ) : -......j..-..-. y g -, y y,. y. i cucsco @ hv t F n.n.c .?. 5, w,w.i l.cso G e n f. \\boxc.s JCx '%A.lC44cp ic)52.13 A,3 /CM'!!S - 0w:u._ _i y A:, c..,,<.q u i.u . i.,=,,,m. _. l / ~. '.. - e,..g l~~,l ~.,1,c.i, / 7 y p,,-,,,y.,, .y !* .~ + x.. r ~.., itv c.? 0 w. {in.n. t,5 ' '7. ** As s ! 7. T /t%'g)'('Of%A ?[/*%$ //// W pflY ffirll *f,t/o hl'0 lllff,f'{ (( /U tl $ b h l ~/ <1 h b ' l . l h/ %g)(~ V Ye $. 'A k:^ ? ?.17. A l2.I ?)'C...'.1-l 2 5 M li. t Y l' % : cw. '- :: ' V. i,'r,..! 1 r'.'S, Y..,.h f., /, (,,IC, 4.II, G,1+ Y'?Stukt'n)-,#m7of l b /s 6.l V M 1f.'. // % 'ht(.9 as] $ 'D /t n fu; Suu.ssNA As 12.3: D h 77,#,,-.G//b /NA'.'/ []h.u.rn-Sil>P /249 'P9M) #W/ /%J (f ~ S At#5 O47(v CN./ AL At-k Ct I. /t-Y AeM@ /T (f/P Illhlt f rVD TD l'GirlhT lt'lGr'V3?L Y */ Al 'i'bS U ST. i h ~'.) 10 ./ / r.-ci. c.r.htt2, i:1 Ca.i 9M /x.'o'L9 x t ' *1-7 ;~t. *,1 '.'r!* l' M 'i~' ~ })h*(Y h )f)?l5; & h* i Y.$h h f, ),.' e . *f l.p)Ll ? /* {*// f ,o s. JW n ' 57~. i V 9 1 --4 .-y -y.- -m-.,, .mm r_.-_.,. w-,-e~,,,,.r,-ym__w....,,--. .w._, ,.--.-,-----,------m-mor..,,.,_,,
1i ._.._m. ~... -... _-.s-- ., aft / Form 34811 (7 81) /'*
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(Formerly SPD 1003-2) T!/. /E1' C ~ (1) ID No: DUKE POWER COMPANY 1-PROCEDURE M/JOR CHANGE Change.Jio : PROCESS RECORD 6ermaneiit;/ Restricted To t k-- r e n (2) ' STATION: I /TAvM (3) PROCEDURE TITLE: b /d /'lx4u Aa# b/#tN'JL'(IAA/ !/197FhfS7W/h 7 ~ ~ (4)' SECTIOi(S)0FP50C5b~URbIhFbCTED: /- , //<O '^ ~ ~ .(5}Y bt) 6.AQ Iol ., DESCRIPTION OF CHANGE: (Attach additional pages, if necessary.) L Ol'/M &' W 'W 5 Y - (i CrJ c.W /I,1 c,s.MC~ "/2 I n;li.! n " Ital Aal? 2 ' (6) REASON FOR CHANGE: O ll s wts L :;awra:Im p up i.v/en 9%dM' Wt A Si m J /- ) # J S & ^ *~' _ i i 'u. ' ,nr.i ~ r.e.!. nam s' 'W,.~~d * ' G - [;,9 **, y * $ l'& y I'.Y CF' ' #' # // (7) PREPARED BY:- / #' # e DATE: ? -I.E-0 4
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m.av- /' (8) SAFETY EVALUATION This change: I Yes No Represents a change to the station or procedures as described 3, in the FSAR, or a test or experiment. not described in the FSAR7 .Yes No Requires a change to the.:tation Technical Specifications? Yes No \\ Involves an unreviewed safety question? If the an.swer to any of the above is "Yes", attach a detailed explanation. As appropriate a'ttach a completed " Nuclear Safety Evaluation Check List" form. By: / / 4.w / Date: 3"l f~N (9) REVIEWED BY: / / h a d .-.DATE: ? -/< - F 9 ,/ -f Cross-Disciplinary Review By: N/R: M + l i i (10) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: l By: Date: s t. (11) APPROVED BY: L~ - / DATE: ?. IT /Pk / v, (12) MISCELLANEOUS: -Reviewed / Approved By: Date: Reviewed /Apprcved By: Date: i- } l 7, (13) Page 1 of l Rev 14 p 9/20/77
og r Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:TP/1/A/1350/25A PROCEDURE PREPARATION Cgange(s)O to _ __ PROCESS. RECORD. Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: D/G 1A Elackout and Load Rejection Preoperational Test !M ADATE: 3-2O (4) PREPARED BY: v i / (5) REVIEWED BY: M D TE: 3- 0-9h. j[I
- R: Of0 84 9 Cross-Disciplinary Review By:
e, v / I (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By; Date: 3 /7!#/ (7) APPROVED 3Y: U-Date: y (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l CONTROL COPY l O e
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TP/1/A/1350/25A DUKE POWER COMPANY CATAk'BA NUCLEAR STATION D/G 1A BLACKOUT AND LOAD REJECTION PREOPERAT10NAL TEST 1.0 PURPOSE 1.1 Verify proper operation of the degraded bus voltage protection on 1 ETA switchgear. 1.2' Verify that: 1.2.1 D/G 1A can start automatically and energize the emergency bus with permanently connected loads within acceptable time limits. 1.2.2 The load shed feature operates properly. 1.2.3 D/G 3A can accept the B/0 design loads in committed sequence and maintain voltage and frequency within acceptable limits. 1.2.4 D/G 1A Blackout auto-connected loads do not exceed the two hour rating. 1.2.5 D/G 1A operates for treater than or equal to 5 minutes while loaded with blackout loads. 1.3 Verify that the D/G can accept the B/0 design loads under an accelerated sequence and maintain voltage and frequency within acceptable limits. 1.4 Verify that D/G 1A can synchronize with offsite power while connected to emergency loads, transfer these loads to the offsite power source and proceed through a shutdown sequence returning the D/G to standby. 1.5 Verify that a hot bus transfer on the B/0 switchgear can be performed once synchronized with normal offsite power. 1.6 Verify that D/G 1A does not trip due to a complete loss of load. t 934 C g-1.7 Verify that DG/1A can reject a load of > 6es-Kk' without exceeding the acceptable voltage and frequency limits. 1.8 Verify that during B/0 actuation, the essential and B/0 trains are independent and isolated from each other. NOTE: The sequencer logic and load sequencing time intervals are verified in TP/1/A/1350/09A - D/G 1A Load Sequancer Preoperational Test. i
~ TP/1/A/1350/25A Pcg2 2 of 15
2.0 REFERENCES
NOTE: The latest Document Revisions (and change order numbers, if applicable) used to develop this procedure are given on Enclosure. 13.1. 2.1 System Descriptions: 2.1.1' CNSD-0114-01, D/G Load Sequencer ~ 2.1.2 CNSD-0120-01, D/G Electrical Controls 2.2 CNS FSAR: 2.2.1 Section 8.3.1.1.3, Standby Power Supplies 2.2.2 Table 8.3.1-1, Maximum loads to be supplied from one of the Redundant Engineered Safety Power Distribution System. 2.3 CNS Tech Specs 4.8.1.1.2, D/G Surveillance Requirement. - 2.4 Reg Guides: 2.4.1 1.108, Preoperational Testing of D/G 2.4.2 1.9, Raquirements for D/G Testing 2.4.3 1.41, Preoperational Testing of Redundant Onsite Electric Power Systems to verify load group assignments. 2.5 One Line Diagrams: 2.5.1 CN-1702-02.01, 4160V Ess. Swgr. IETA 2.5.2 CN-1702-04.01, 4160V B/0 SWGR 2.5.3 CN-1703-01.01, 600V Ess. 1ELXA, IELXC 2.5.4 CN-1703-04.01, 600V B/0 LC ILXI, ILXH 2.6 OP/1/A/6350/02, D/G Operation 3.0 TIME REQUIRED 3.1 'Gue (1) Test Coordinator - 16 Hours 3.2 One (1) Control Room Operator - 16 Hours 3.3 One (1) Performance Technician - 16 Hours 3.4 One (1) Nuclear Equipment Operator - 16 Hours NOTE: The preparation of this test requires lining up of several other systems.
TP/1/A/1350/25A Pags 3 of 15 4.0 PREREQUISITE TESTS None 5.0 TEST EQUIPr!Eh7 5.1 Digital Multimeter (Fluke 8600A or equivalent used only to verify absence of bus voltages) NOTE: The D/G High Speed Visicorder on the IDGPA Panel will be used to take data. 6.0 lit!ITS AND PRECAITTIONS 6.1 Refer to limits and precautions of operating procedure OP/1/A/6350/02, Diesel Generator Operation. 7.0 REQUIRED STATION STATUS M / 2fft.1 Ensure that referenced drawings and system descriptions are the latest revision in ?! aster File or have been reviewed on 3.1. 8.0 PREREQUISITE SYSTEt! CONDITIONS }~c %74v *> I2.I 1Mt.A e /2.*f '- C.>;g. A'M' /1-M.1 Open Link B-17 in 1ELCP0112 to reposition 1ABF-D-11, 13 g /22L%@i_/.5/.it/tyt&lNtf 6.I, t Chuw c:-+1w ter% tr>sawW waar AwAM 6m.n&A and 16 (CNEE-0166-01.47) N gV If performance of this procedure is suspended for any
- "O -
CAUTION: p reason for a period exceeding 24 hours, this' modification must be returned to normal, or the proper station modification procedure must be implemented per Station Direct 1\\e 4.4.3. Rggag / 2. e nntsu-e- / 2. 5 % l47 8.2 Perform the following to prevent the Blackout tiotor Control u g Centers from transferring to their alternate sources. %/ 9-NY 8.2.1 Ensure selector switch for ILXN-4C (ALT FDR TO ltDN) l is in the !!ANUAL position. [/M944 8.2.2 Ensure selector switch for ILXN-SD (ALT FDR TO 111X0) is in the ?!ANUAL position. l [d~/ 7 DO 8.2.3 Ensure relector switch for ILXB-5D (ALT FDR TO lt!XQ) is in the ?!ANUAL position. CQ k /3d,$I E,t50c.7M/7.i
- 2 77 M A P /7 3 S 8.3 All systems that will be sequenced into operation have g
been filled, vented and aligned as specified in Enclosure 13.3. M/hW84 The Unit 1 Operational Aid Computer (OAC) is opwational. M/IN .5 The Unit 1 Diesel Generator 1A, along with all support l systems, are operable and aligned for B/0 actuation. D/G 1A visicorder must also be operable, pt g ji;t kta.M /2 I 11M& I2 *3'- U yf" N / 8.6 The Unft 1 D/G Load Sequencer 1A is operable. /' 12YG I Am4~nJwnne amw Mc PR-ZD.+os.mi.+tc D-z.s w wh causure a noceorrS/s wn:atwwncu oo. J-LIV h.'Ihk.. '1.t \\~~ a :-T Fehsu. A '".7 9 9 l
e,. TP/1/A/1350/25A Page 4 of 15 yg $;k.;ue. /7. In A.i)& 3** /rf 8.M The following pumps are operable with no deficiencies noted. Items 7 to be checked include oil reservoir levels, ventilation path available for motors, no mechanical interference, manual isolation valves open and no red or white tags. 1/'H@ 8.7.1 RN Pump 1A M/ S 2M+ 8.7.2 NV Pump 1A g/ 3 Efrh1-S.7.3 KC Pumps 1A1, IA2 g / F2$ S.7.4 CA Pump 1A y /%,.-.. / &>d Sw mai.t@cA A!OvSi,v Gwr 1./W Angr,wpo. k/A?fef8.8 Ensure that the Auxiliary Shutdown Panel Transfer Switch remains in the Control Room position throughout this test. g/ F28Y.9 Ensure that the SSF transfer switch remains in the Control Room position throughout this test. f[a M/_ zgf k ki,7w.u /2. t TIrGid + 12. *3 '- 8.10 Ensure electrical alignment on Enclosure 13.4 is complete. j c,r,. k /k2 N.11 gg 'ybontactnWs/'2. I httW /2 ~5 *. I-p I&E and verify that the equip' ment necessary to take the load profile for the Vital & Diesel batteries has been installed. M N N.12 Ensure the following event recorder and computer points / are checked out: IER282 1 ETA Norm Inc FDR Open IER284 1 ETA DG Bkr Closed A0575 4KV 1ETB Bus Voltage h, SVGRIETADegradedBusVoltageTriphg g,d,s.m p IER584 .e.,7a.r.wj Fcrs/v Sum aJ A0574 4KV Bus ETA Feed From D/G A MW N/ 3'N 3 Record multimeter to be used for Section 12.1 information: ID o CNIAcl9h3 bh/2 h Cal. Due Date T / k.14 sq,:$%s l'2.( rrMNto /*Z.*3 '. O S2 Annunciator IAD11.07.06 "SWGR 1 ETA Degraded Bus Voltage" 4-gYog&I$ ElstScran /2 4 fir.0l'Z,5 DitrSet d>uwyrast/$ /S CMUYDrL has been turned over from Construction. c y 9.0 TEST METHOD F,h'AtsCD mDF cFiSt4~' /Twc,2. The degraded bus voltage logic is verified by demonstrating the alarms and tripping functions on the normal incoming breaker to the 4160V Essential Switchgear work properly. The degraded bus voltage tripping function then initiates a Blackout Loading Sequence (committed) on the Train A Blackout and Essential Switchgears. Train B Blackout and Essential Switchgears have been de-energized for the test to verify j independence and isolation from the Train A Switchgear through the use of bus voltage measurements. Proper operation of the load shed, diesel C " P k> start and sequencer actuation are verified. The D/G is verified to F maintain voltage and frequency within acceptable limits during and after j I f A g&t+ the' loading sequence. Total Blackout Auto Connected Load is verified n'ot bwhti Sanp I L s.v Wh t % '* rt'trn - m.tn,.u,g,,ll R,.;a.uw.~L. i trhtun /2.*/ > 17./tc i% v.c.Nuys w Hs t=~ In.cr,. 2 u s,cn..~,2. i m. t 19.s 1'15,12a 3 iL.I int.,4.n /2.*t s twic p s.guz jug $ ty O t. 54 A.o g.,.,rN tihM ,i,wors ru c1"et.'t c Rw.%r> r rsasn.. ms...n.2 iav.twws.. e C/6I7%*$ Sti'/w',T, .a c.s,. W 50'C.t.
Ff .,c,y8 y", - TP/1/A/1350/25A W/Wg6 Pagn 5 ef 15 g,\\% }~w san.s. I 2.I nmwen l'2.'l' ID4tC hN11 n~oi;is,v3 SS95 c/sina ~ siccw MT-to exceed the two hour D/G rating. The D/G is then verified to be able to be paralleled to offsite power, transfer its loads to the offiste power source and pro:eed through a shutdown sequence returning it to standby status. The degraded bus voltage logic is then verified to properly trip the 4160V Essential Switchgear alternate incoming breaker. The degraded bus voltage tripping function then initiata.s a blackout loading sequence (accelerated) on the Train A Blackout and Essential Switchgears. The D/G is verified to maintain voltage and frequency within acceptable limits during and after the loading sequence. The hot bus transfer function between the normal and alternate incoming breakers to the B/0 Switchgear is verified to operate properly when the D/G is paralled to the offsite nower source. Finally, two load rejection ter.cs are performed on the D/G. First a load rejection equivalent-to the largest single load (1 834 KW) is performed followed by a full load (3 7075 KW) rejection. During both load rejection . tests D/G parameters are verified to not exceed acceptable values. 10.0 DATA REQUIRED 10.1 D/G Voltage - Visicorder 10.2 D/G Power - Visicorder 10.3 D/G Frequency - Visicorder 11.0 ACCEPTANCE CRITERIA bl 11.1 The degraded bus voltage protection circuit operates properly as fff described in Sections 12.1 and 12./Z. 11.2 The D/G can: 11.2.1 Start automatically and energize the emergency bus with permanently connected loads in < 11 seconds. 11.2.2 Properly load shed those loads as described in Section 12.1 11.2.3 Maintain its frequency at not less than 95% of nominal and returning it to within 2% of nominal in less than 60% of each load sequence time interval. (For both committed I and accelerated loading sequences). 11.2.4 Maintaining voltage at not less than 75% of nominal and returning it to within 10% of nominal in less than 60% of each load sequence time interval. (For both committed and accelerated loading sequences). t 11.2.5 Operate for greater than or equal to 5 minutes while loaded with blackout loads. 11.3 The auto connected total load to the D/G does not exceed 7617 KW. l
i, TP/1/A/1350/25A Pagt 6 of 15 11.4 The D/G can: 11.4.1 Synchronize with the offsite power source while the D/G is Ioaded with its emergency loads, 11.4.2 Transfer its loads to the offsite power source, and 11.4.3 Be restored to its standby status. 11.5 The B/0 Switchgear Hot Bus transfer operates properly as described in Section 12.3. 11.6 The D/G rejects a load of 3 7075 W without tripping. The D/G speed does not exceed 500 RPM during and following the rejection. 11.7 The D/G rejects a load of 2 834 W while maintaining voltage at 4160 1 420V and frequency at 60 i 1.2 Hz. 11.8 Train A and B Essential and B/0 Power Systems are independent of each other by showing the following: 11.8.1 Train B Essential Buses and B/0 Buses remain without voltage during Train A operation. 12.0 PROCEDURE CV NCTC. Si ncas i2 I Tn;uu.4-l 2..'$ AK SGXwnttL frv) C pt u g,g ** g ); gig g y p p N ( g G Q, Initial /Date Citner4 i'2.4 ebo 17.T /62( /eXA'WCC Ma/Av ( AvrWmoW / BsMC at hfD2 %LRM i 2.t T]hfM-s+ /2.S 12.1 Train A Blackout Loading (Committed Sequence) and Degraded Bus Voltage Verification (Tripping 1 ETA 3) h/ ') 'If* N 12.I'.1 Ensure that Prerequisite Tests, Required Station Status and Prerequisite System Conditions for this section are completed and met as required. N/F2B # 12.1.2 Open Test Switch H on test block PD located on /2M /p//r IEATC16. CAlTTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. k/ 19% 12.1.3 Open Test Switch H on test block PE located on S /Jfd / p g y. IEATC16. CAUTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3.
t. - TP/1/A/1350/25A Pagn 7 of 15 CA WION: Do not leave this switch open any longer than necessary to verify annunciator. Actual B/0 will occur after 10 minutes. Q/1~LfrW 12.1.4 Verify that annunciator 1AD11'07.06, "Sk'GR 1 ETA Degraded Bus Voltage", alarms after approximately 40 seconds. WN /W #gry 12.1.5 Close Test Switch H on test block PE located on g/ 1EATC16. [ /}29" U 12.1.5.1 Verify annunciator IAD11.07.06 clears. / ~3-2C-D 12.1.6 Open Test Switch H on test block PF located on /3/v//r 1EATC16. CAUTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. CAWION: Do not leave this switch open any longer than necessary to verify annunciator. Actual B/0 will occur after 10 minutes. M/ NN 12.1.7 Verify that annunciator 1AD11.07.06, "Sk'GR 1 ETA Degraded Bus Voltage", alarms after approximately 40 seconds. / S2O O 12.1.8 Close Test Switch H on test block PD located on / /ppy 1EATC16. M/g@ 12.1.8.1 Verify that annunciator IAD11.07.06 clears. [df/S2 N 12.1.9 Open breaker 1EDF-F01F to disable D/G Load Sequencer IB and verify loss of power by Control Room alarm. ((/ N'N Y 12.1.10 Open IETB3 (Normal Incoming Feeder to Train B Essential Switchgear) and 3GTB1 (Normal Incoming Feeder to Train B B/0 Switchgear). (There should not be a breaker in IETB4 cubicle.) [/%18 bI 12.1.11 Open breaker ICDB-F02I to disable IFTB/1GTB Control Power. 12.1.12 Open the following breakers to de-energize Train B 125 VDC Vital and Diesel Power Systems: [6/ SN'N 12.1.12.1 1EDB-F02A (Verify loss of voltage by meter on 1EDB) I f
TP/1/A/1350/25A Psga 8 of 15 % /M N b 12.1.12.2 1EDD-F02A (Verify loss of voltage by meter on IEDD) gf/34Nb 12.1.12.3 IDGCB Battery Breaker (Verify loss of voltage by meter on 1DGDB). M/3 LW 12.1.13-Open Sliding Link G-6 in Panel 1-DGLSA-1 to g/g8[Bli disable Accelerated Sequence Relays EA (AA1), and EB (AA2). This will allow the Diesel Generator Load Sequencer to load using the Committed Sequence only. CAUTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. /I/N' 12.1.14 Verify that D/G 1A is in standby and capable of operation. Have D/G Coordinating Engineer prepare the D/G Visicorder such that D/G voltage, frequency and power can be recorded. / S7 12.1.15 Have I&E start Multipoint Recorder to obtain load profiles of the Vital & Diesel Batteries. / 12.1.16 Open Test Switch H on test block PE located on g/ 4/ry' IEATC16. CAUTION: 'If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. M/M 12.1.17 Verify that annunciator 1AD11.07.06, "SVGR 1 ETA Degraded Bus Voltage", alarms after approximately 40 seconds. 12.1.18 After approximately 10 minutes: I /,$N 12.1.18*.1 Verify that 1 ETA 3 (Normal Incoming Feeder to Train A Essential Switchgear) is tripped and immediately perform Step 12.1.18.2 [ / SM' 12.1.18.2 Trip ITA4 (XFMR 1ATC Feeder Breaker). [MMO 12.1.18.3 Verify that IGTA1 (Normal Incoming Feeder to Train A Blackout Switchgear) is tripped. M/ h b 12.1.18.4 Verify that D/G Load Sequencer 1A is actuated. m.-
e,- TP/1/A/1350/25A Page 9 of 15 k/StM 12.1.18.5 Verify that D/G 1A starts. /94 M 12.1.18.6 Close Test Switch H on test block PE /ph loaded on 1EATC16. / }2M 12.1.18.7 Close Test Switch H on test block PF /p/ft/ located on IEATC16. T /3A M 12.1.18.8 Verify that event Recorder Point ER584, "SWGR 1 ETA Degraded Bus Voltage Trip" has occurred. 12.1.19 Verify the following actions occut approximately 8.5 seconds after D/G start (may be verified visually or through the use of Control Room Alarms): %/N 12.1.19.1 1ETAS (XFMR 1ETXA FDR BKR) remains closed. Q/ '31 12.1.19.2 1 ETA 6 (KC PUMP MTR 1A1) is tripped. /@h'/ N 1 ETA 7 (KC P'MP MTR 1A2) is tripped. 12.1.19.3 U % /'M 12.1.19.4 IETAB (NS PUMP MTR 1A) is tripped. [/ 'hd' 12.1.19.5 1 ETA 9 (ND PUMP MTR 1A) is tripped. k/IW 3 12.1.19.6 1 ETA 10 (XFMR 1ETXE FDR BKR) remains closed. N/ '3 2M 12.1.19.7 1 ETA 11 (NI PUMP MTR 1A) is tripped. g [/g,29-M 12.1.19.8 1 ETA 12 (NV PUMP MTR 1A) is tripped. / 3N 12.1.19.9 1 ETA 13 (CA PUMP HTR 1A) is tripped. [f/ 3-20-d 12.1.19.10 1 ETA 14 (RN PUMP KTR 1A) is tripped. M /3 M b 12.1.19.11 IETA15 (KF PUMP HTR 1A) is tripped. [$~/34 M 12.1.19.12 1 ETA 16 (XFMR 1ETXC FDR BKR) remains closed. %/3-lf'N l 12.1.19.13 IETA17 (A/C COMP FDR) is tripped. K/NE'k 12.1.19.14 Valves ISA2 and ISAS open. NOTE: Have someone stationed at 1ELXA and IELXC to verify the following two breakers. / 3'bb 12.1.19.15 1ELXA-4B (NORM INC BKR) is tripped. l f l
TP/1/a/1350/25A Page 10 of 13 h" /34 12.1.19.16 1ELXC-4B (NORt! INC BKR) is tripped. NOTE: Have someone stationed at 1LXI to verify the following breaker. [/ 12.1.19.17 ILXI-5D (ICCA FDR BKR) is tripped. k [h16 12.1.20 Follow the following sequence of events. Verify proper equipment actuation on Enclosure 13.5. TIME EVENT 0 Sec Initiation B/O 8.5 Sec Load Shed 10.0 Sec D/G BKR (1 ETA 18) Closes 11.0 See IETA2 and IFTA1 Have Closed Load Group 1 energized. 12.0 Sec Load Group 2 energized. NV Pump 1A starts. 15.0 Sec Load Group 3 energized. 30.0 Sec Load Group 6 energized. KC Pumps 1Al and 1A2 start. 35.0 Sec Load Group 7 energized. RN Pump 1A starts. 40.0 Sec Load Group 8 energizes. CA Pump 1A starts. 60.0 Sec Load Group 10 energizes. 10.0 Min Load Group 11 energizes. Control Room and Control' Room Area ventilation starts. 11.0 Min Load Group 12 energizes. Control Room Chilled Water Compressor Motor starts. 12.0 Min Load Group 13 energizes. [/ 9'bb 12.1.20.1 Allow D/G to operate for > 5 minutes with Blackout loads connected. Q7 M9' 12.1.20.2 Record D/G Auto-Connected Load per computer point A0574 on Enclosure 13.10. 12.1.21 After start verification of KF Pump 1A is c complete, reset the following signal: [/ 11k 12.1.21.1 Reset D/G Load Sequencer 1A. 12.1.22 Verify absence of voltage on Train B Essential and Blackout Power Systems as follows: d /'3-7.f' O 12.1.22.1 1ETE Bus through computer point A0575 "4KV 1ETB Bus Voltage" k/ 34 12.1.22.2 IFTB Bus using local voltmeter on 1FTB Bus. 1
TP/1/A/1350/25A Psgs 11 of 15 12.1.22.3 The following Essential and B/0 Lced Centers through their local vo1* meter: K / 3-26'N 12.1.22.3.1 IELXB Q/ PLf-94 12.1.22.3.2 1ELXD g /'3-l N 12.1.22.3.3 ILXH g Tr$'MI 12.1.22.4 The following 600V Essential and B/0 Motor Control Centers using a Digital Multimeter: [/3 26-$ + 12.1.22.4.1 1EMXB M/ S-L 12.1.22.4.2 IEMXD M/ 5-29'%+ 12.1.22.4.3 IEM.T \\ R/ ~b-LS-N 12.1.22.L.4 1EMXJ N /~3-29 M 12.1.22.4.5 1EMXL M / 9-l8 O 12.1.22.4.6 IEMXR - (,\\t / 12.'.22.4.2 1:02-: / 12-I.22.4.0 1"XR. 12.1.22.5 The following 120 VAC Essential and BJO Power Panel Boards using a rigital Multimeter: g /7,LS-B4-12.1.22.5.1 IEKPJ M/ S'L9'6+ 12.1.22.5.2 1EKPB g2MF"/ M 9'6 # 12.1.22.5.3 IEKPF / 12.1.22.5.i IX'X 12.1.22.6 The following 125VDC distribution C centers through their local voltmeter: --/ 12.1.22.'.1 1CDB /'Af/ 346'N 12.1.22.6.2 1EDB N/71W 12.1.22.6.3 IEDD MF/340 12.1.22.6.4 1DGDB 1
^ TP/1/A/1350/25A Prge 12 of 15 ([/3'1 12.1.23 Transfer breaker from 1 ETA 3 cubicle to 1 ETA 4 cubicle. ~ h F / k'lS N 12.1.24 Close breaker ITA4 (XFHR 1ATC FDR BKR). 8/!f /S1W 12.1.25 Have Operations parallel D/G 1A following OP/1/A/6350/02, Section 5.fi. NOTE: Train B Essential and Blac4out Power Systems may be re-energized at this time. [/ 12.1.26 Attach and label a copy of the Visicorder chart to this procedure as Enclosure 13.6 "D/G Parameters During Committed Sequence Loading". Record actuation times for event recorder points IER282 and 1ER284 on Enclosure 13.10. M/ 3'd 12.1.27 Close Sliding Link G-6 in 1DGLSA-1. N/1l23)2If [///'/3-2G 12.1.28 Have Operations reduce D/G 1A load and then shutdown D/G 1A per OP/1/A/6350/02, Section 5.0. 12.2 Train A Blackout Loading (Accelerated Sequence) and Degraded Bus Voltage Verification (Tripping IETA4). //6 3-3t-ff [/}29M 12.2.1 Verify that D/G 1A is in standby and capable of operation. Have D/G Coordinating Engineer f4f 3-3r-M prepare the D/G Visicorder such that D/G voltage, Og 9f yJ.Ygt:-f4 A frequency and ower can be recorded. P."In uh-~ 6/2 gMilcc5 tril.tt)A fDYNecI or/w; /%Slinr t2 67 r,ggy.3,u Jg.2, t. I s hpe# YsNdtYH [t tbN ( 1/h / N ' N 12.2.2 n p ,,,pg fiM / 3/Nff'l on 1EATC16. j3gy s jz pg p,.,4f; m Icoa-Fas6. CAUTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification must be returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. M /.N'W 12.2.3 Open Test Switch H on test block PE located A/gtf on IEATC16. CAUTION: If performance of this procedure is suspended for any reason for a period exceeding 24 hours, this modification mest he returned to normal, or the proper station modification procedure must be implemented per Station Directive 4.4.3. 12.2.3 After approximately 10 minutes: I /3'M 12.2.4.1 Verify that IETA4 (Alternate g 3 3,.q4 44 f.#/r'( Incoming Feeder to Train A Essential I i Switchgear) is tripped. /gyge 4/)fAfft1 g'/3 z /$ 2 I I S.s " /*.L s*/'J2 J%% rpay C4,o ( -3.9,sv )[t[tQI I l n fct?m, l j f i .. J vn nca cxtw a:n..,r wingaywrz y,;,wuS ivi r fx,,,.a y }$.,f' l .*'t / ftann w ns'Fimj t l Ol# 1 / z.t.t.h.fWe Nr p3 ftL,y e opts. H-l 77 ll wILXs' Cit 2 '70 t%W h& n a n - i m tr.v, m m w-rer w w - > < - Cnm FM - g,,,,. c,, ,se,97 c.s q.. t
Q-TP/1/A/1350/25A Pagi 13 of 15 ' grY/ '5'W-b+ 12.2.4.2 Verify that D/G Load Sequencer 1A is actuated. k '39/O 12.2.4.3 Verify that D/G 1A starts. //F 7'M 12.2.4.4 Close Test Switch H on test block PD / i,T.~/PCfM3/3//ty \\ j located on IEATC16. 5 W/ ~55 eft-gF 12.2.4.5 Close Test Switch H on test block PE g/ggp located on IEATC16. , [JK/ 94t-d 12.2.5 Verify sequanter sheds loads and commences n $/'* /s),2 S.l ? D LEstugus&W* is'ltt{!TW'M s.r $.4c w the s equ.c /H S R.h..s t., < l, C:.'sJHT *te its loading /g'/'M'dO'I-12.2.6 Al encer to comple. ,)y' sequence. [2.L hl W gA//% g g.AQ Aft 61Na'd}ng compIe$on, fggM 6 8/c /A.M~.5 v8savs g,_Wr/$ 'h-f v- 12.2.7 reset D/G Load Sequencer '1A. ' h7 YOlO 12.2.8 Transfer breaker from 1 ETA 4 cubicle to 1 ETA 3 cubicle. f iM N'O / 12.2.9 Have Operations parallel D/G 1A following { OP/1/A/6350/02, Section 5.0. [hI~/3 */W 12.2.10 Attach and label a copy of the Visicorder chart to this procedure as Enclosure 13.7 "D/G pic i - f S.'P O g'@ syr C.y.vsta-n.% sh1cnA w N our ru,"S7' cn parameters During Accelerated Sequence Loading 'A'gg i /" l'hs='d 12.3 Blackout Switchgear 1GTA Hot Bus Transfer Verfication k/ kWh 12.3.1 Ensure Diesel Generator 1A is still operating paralled with offsite power. M/3 }fD 12.3.2 Depress the close pushbutton for 1GTA1 (Normal Incoming Feeder to IPTA Blackout Switchgear). k/bMO 12.3.3 Verify 1GTA1 closes, k{ M/3"T N 12.3.4 Verify 1 ETA 2 and 1FTA1 breakers have tripped. 12.4 Diesel Generator Load Rejection Verification (Equivalent to Largest Single Load) ! N/ M'fA 12.4.1 Ensure Diesel Generator IA is still operating S paralleled with offsite power. [I/3M 12.4.'2 Adjust Diesel Generator load to > 834 W. Record load per computer point A0574 on . 3.10. M/ N'fb 12.4.3 Start visicorder to monitor D/G voltage, frequency f and power. S' 6 12.4.4 Trip IETA18 (D/G 1A Breaker). l 4 t'2. u.i I jnxt' f 2..'t.4.(. L # 191J *< L'. 4 i t i. e.<.3 /sa fa i ( 2 7 t L'4 / k/'X
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c. TP/1/A/1350/25A Psge 14 of 15 / NMI 12.4.'5 Stop Visicorder. M /3 @ IA-12.4.6 Attach and label a copy of the Visicorder chart to this procedure as Enclosure 12.6 "D/G Partmeters During 1634 W Load Rejection". S 'Z. NpF UI~',~I, D5SikI.f P_i 9..'). I' I* l IN .,.. ~, 12.5 Diesel Generator Load Rejection Verification (Full Load) M/ NY 12.5.1 Ensure Diesel Generator 1A is still operating paralleled with offsite power. ((/E 12.5.2 Adjust Diesel Generator Load to E 7075 W. Record load per Computer point A0574 on 3.10. M/ 12.5.3 Start Visicorder to monitor D/G Voltage, Frequency and Power. M / 12.5.3 Trip IETAIS (D/G 1A Breaker) {/r~/ 12.5.5 Stop Visicorder. 8/f/$4D'N 12.5.6 Attach and label a copy of the Visicordar chart to this procedure as Enclosure 13.9 "D/G Parameters During Full Load,(3 7075 W) Rejection". 12.6 Restoration of Modifications ,. 9 g f' 312.6.1 Close link B-17 in 1ELCP0112. C/W / /M hhh &- /4 'f2.u.2. Ame*~).'nkt kdc55 %D4 t-!w.c F-lAnaP2 w IL4hY%- '~ 12.7 Acceptance Criteria Verification f/f/i'lO.7.1 Verify Acceptance Criteria 11.1 is satisfied as demonstrated in Sections 12.1 and 12.2. 12.7.2 Verify Acceptance Criteria 11.2 as follows: I @/'Y t@ 12.7.2.1 Verify 11.2.1 is satisfied demonstrated in Section 12.1 and documented on Enclosure 13.10. I / 12.7.2.2 Verify 11.2.2 and 11.2.5 are satisfied as demonstrated in Section 12.1. i [M/ 'IN 12.7.2.3 Verify 11.2.3 and 11.2.4 are satisfied by using the Visicorder Printouts attached as
- 3.6 and 13.7.
'N# / 12.7.3 Verify Acceptance Criteria 11.3 is satisfied using the - values recordedgn Enclosure 13.10. n,1 c h h / 2.t. y.'!- H i.? &. 2 l 4 30 [ h f'/ ' 2.7.4 Verify Acceptance Criteria 11.4 is satisfied as I demonstrated in Section 12.1. terAvNf3gi dfgSW/3** k L,) fws 'C L',1M iMSS &,M piin [- SQ AA/Wd a,,,,.,,,n,,, _ g,g 4,n w ,e,a 02 e a o cn:se a m w"6 RmiJ. Jaw, . r caw m r 42.s:re-n- (Sxwm.reo swre ti s.s m s.i )
e, 3It f d1013/JbY WJ22'*H G-G 95sucJaa,eea rioacn c,&gs c-g s.w. 0-35 /N /L1Cf-ClIis N 'l'!l* WlE*$2.6 2 l Law son,an />csoss om.s H-l wolf I ip J C2h00ll2 - G 6 9 0 c 4
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TP/1/A/1350/25A Page 15 of 15 44Y /W/ Verify Acceptance Criteria 11.5 is satisfied as demonstrated in Section 12.3. /Od / 1.7.6 Verify Acceptance Criteria 11.6 is satisfied by using the Visicorder Printout attached as Enclosure 13.8 and 3.10. /bi(II b 2.7.7' Verify Acceptance Criteria 11.7 is satisfied by using the Visicorder Printout attached as Enclosure 13.9 and 3.10. k/k .7.8 Verify Acceptance Criteria 11.8 is satisfied as demonstrated in Section 12.1. NOTE: Upon completion of this test, a Work Request should be generated to have I&E place annunciator 1AD11.07.06 in service. 13.0 ENCLOSURES 13.1 Document Revisions 13.2 Reverification Form 13.3 System Lineup 13.4 Electrical Alignment 13.5 Equipment Operation 13.6 D/G Parameters During Committed Sequence Loading 13.7 D/G Parameters During Accelerated Sequence Loading 13.8 D/G Parameters During 3 834 KW Load Rejection 13.9 D/G Parameters During Full Load (3 7075 KW) Rejection 13.10 Event Recorder Actuation Times and D/G Load Values
I'"g2 1 of.J CATAW15A Nt;t.LLAN SI A110N - D/G 1 A B/O AND LOAD REJECTION -PREOpERATIONAL TEST TP/1/A/n50/25 A ENCLOSURE 13.1 DOctfMENT REVISIOils Documents listed below are referenced in Section 2.0. Verify the latest IndJeated revision number nnrces with the latest revision in the Master File. If any reference la out of date, a qualified reviewer must ' review the current revision to ensure that the revision will not affect j procedure changes are made ff a revision would affect the perfoimance of this procedure or ensure that adequate the procedure. J Document this review on this enclosure by filling In the reviewed revision (and change order number II appilcabi ', reviewer's name and date of review. 4 4 J 2.1.1 CNSD-0114-01 2.1.2 CNSD-0120-01 2.2.1 FSAR 8.3.1.1.3 2.2.2 FSAR Table 8.3.1-2.3 Tech Spec 4.8.1,l.2 3 l Rev. 6 Rev. 3 Rev. 7 Rev. 7 1 Rev. 3 i Rev. CO Review Rev. CO Review Rev. CO Review Rev. CD Review Rev. CO Review Date Date Date Date Date j flo. No. by No. No. by !!o. No. by No. No. by No. No. by M 3ze9+ [ )6f7 3-ZBli -6 M 5-2Sof i = l 4 T 1 ) i .-...~.~T.;_."....'f_~.:----~ .. * * - -. 7 - .T.. _. . *--.. _ -**'..-*."., ;.;* --. : - ;*;*. 1; _.. 2 eee
As AA1AWuA f*t,LtnK btAttuN twge 4 ot J D/G 1A t/0 ANI) 1.OAD RE.IECTION PREOPERATlOi?AL TEST Tr/1/A/1350/25A ENCLOSURE 13.1 110CUMENT ItEVIS'1ONS Documents listed below are referenced in Section 2.0. Verifythelatestindicatedrevinfonnum5cranrcenwiththe Intest revision In the Master File. If any reference is out of date, a qualified rs procedure changes are made if a revision votild af fect the procedure. revision to ensure icwcr must. review the current 1 Document reviewer's name and date of review.this review on this enclosure by filling Jn the reviewed res infon (and change if applienble), 4 2.4,1 Reg, Guide 1.108 2.4.2 Reg. Guide 1.9 2.4.3 Reg Guide 1.41 2.5.1 CN-1702-02.01-Rey. 1 2.5.2 CN-1702-04.01 Rev, 2 Issued 3/16/73 Rev. 14 Rev. 9 Rev. CO Review Rev. C0 neview Rn m Ruis p No. No. by No. No. by No. No. by No. No. by No. ' No. Date Date Date Date by 1 i 1 l ~~
Unlessun libbLt.nh blh110ft - -P;ga 3 cf 3 D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAi, TEST 1 TP/1/A/13SU,25A C4 CLOSURE 13.1 110CUMENT REVISIONS Documents listed below are referenced in Section 2.D. Verify the latest indicated revision num5cr agrees witti the latest revision in th ?! aster File. revision to ensure that the revision will not affectIf any reference is out of date, a qun11fJed reviewer must review the current the performance of. thin procedure or cunure that nelv spia t r-procedure changes are made if a revision would affect the procciture. Document reviewer's name and date of review.this review on this enclosure by filling Jn the reviewed revlsion (and change order n c, 2.5.3 CN-1703-01.01 2.5.4 CN-1703-04.01 2.6 Ch. OP/1/A/6350/02
- 2
_ Rev. 3 Rev. 8 p proval: 1-30-84 Rev. CO Revim Date Date Date llate Date No. No. by No. No. by llo. No. by No. No. by _ No. No. by M N elke N
- hkW NM G =a e-g my e afw gem gew a w enum D seeee NM 6h Nm-N efDN 6
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Page 1 of I CATAWBA NUCLEAR STATION D/A 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.2 REVERIFICATI N FORM /2dif &D(_/SF-W / / / / ~ / / / / / / / / / / /' / / / / / -/ -/ / / / / / / / / / / / / /- / / / / / / / / / / / / /- / / / / / / / / / / / '/ / / / / / / / / / / /- / / / / / -/ / / / / / / / / / / / / / / / / / / / / / / / / / / / ~/ / / / / -/ / / / / / / / / / i / l / /
Page 1 of 4 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.3 ALIGNMEhT OF AFFECTED SYSTEMS Chemical Volume and Control System (NV) [l7 /3-2.0-D'9-Align the Boric Acid Transfer Pump 1A for Recirculation per OP/1/A/6150/09, Section 9.0. ffY / ' Align the NV System per OP/1/A/6200/01, Enclosure 16.1 with the 3 following exceptions or conditions: ' [6 / 3-ZS M INV294 NV Pumps A&B Disch Flow Cntrl - Closed 6 /'3-Z94+ INV293 NV Pumps A&B Disch Cntrl Isol - Closed [Af / 3 29M INV202B NV Pump A&B Recire Isol - Oper. [/h' / -ZOO INV203A NV Pump ASB Recire Isol - Open 3 [A f /3 46 N INV252A NV Pump Suct From FWST Closed M / T 46 @ INV253B NV Pump Suct From FWST Closed / M /'3>l6 O INI9A CCP To C-Les Disch Isol - Closed M/ 2,49NINII0B CCP To C-Leg Disch Isol' - Closed ('/Jf / N NV Pump 1A Running Component Cooling System'(KC) k / 3'I M Align the KC System per OP/1/A/6200/05, Section 3.0 for Train A operation with the following conditions or exceptions: W O [Af~/ 94@ 1KC56A KC TO ND IIx 1A Sup Isol - Giuseu dFE'M M/ 3'Z9'99-IKC81B KC To ND Hx 1B Sup Isol - Closed [/f' / ~349N KC Pumps 1A1 and 1A2 - Running l Auxiliary Feedwater System (CA) k / 3 lb Align the CA System for standby readiness per OP/1/A/6250/02, Section 3.0 with the following exceptions or conditions: g 6,' M/3'$N CA Purcp 1A Auto Start - ~ m uu M(T / 3 "ZN CA Sys V1v Ctrl Train A & B - Reset [T/3 I6'N Valves ISA2 and ISAS Closed WJ 9' VAuscs lCA%A, \\Cir %A, \\CP S29 Ana ICAG48 c t.csCV
Page 2 of 4 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.3 ALIGNMEhT OF AFFECIED SYSTEMS 6 $Z9 M 1CA71 CA Pump 1A Disch To UST Dome Throttle - Open .h~ /3-l@ ICA72 CA Pump 1A Disch To UST Dome Throttle - Open M /3-M 1CA179 CA Pump 1A Disch To UST Dome Throttle - Throttled to 500150 gpm [ f / N N CA Pump 1A Running Containment Ventilation System (VV) M/ 3 !&N Align the VV System as follows: //ti /31GM Place the following switches in AUTO on IMC-3/iNP dMvi ~ ThusA 6 c.4YuaA;wf VV UPR CONT RET FAN 1A VV UPR C0hT RET FAN IC M~ /S-2fr04-Place the following switches on IMC-3 to M/WAXjko end Phh /9aC0!W/tDivn : VV UCVU 1A VV UCVU IC M /8-76 M Place the following damper control switches on IMC-3 to ALTf0: 4 Lower Containment Vent Damper ILCVU-D-1 %y Lower Containment Vent Damper ILCVU-D-3 i M /'3464+ Place the followl'ng switches on IMC-3 in the NORM position: VV LCVU 1A MAX VV LCVU 10 MAX l M. / $49 f4 Place the following switches on IMC-3 in the OPP #t6//- positionko L2vscWFMS AaC OAst#W': I-l VV LCVU 1A VV LCVU IC F / 3'l9N Place control switch for Pipe Tunnel Estr Fan IA to-Off position on IMC-3 <1/wpO 5 WCfMV e 5 C"UME - l N/60 [ Y 3,2 5 Y e l ; c ; t h,,o n g o l y.k fc b i / Incore Inst Bstr Fan IA n STCP ~aai:n n IMC 0- ,s cAyuh7Me.
I *. Page 3 of 4 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PRE 0PERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.3 ALICNMENT OF AFFECTED SYSTEMS M/ 3-M Gv$vac j>rtAutua /~M / Int"OfVitM1H ; Plese ths fellv ius s iwhs; :n IMC-3 #n the OFF' y3 _u, cy I CED VENT FAN #1A CRD VENT FAN #/IC, 7 /3 -lEdi Place the control switch for the Incore Inst Rm AHU 1A to the g position on IMC-3/v e s s ML-5 W ~ Ik CuYlinM. Nuclear Service Water System (RN) g'f /~f2th+1 Align the RN System per OP/1/A/6400/06C, Section 3.0 for the startup of Train A with the following conditions: $/ 8-@6'l-Place the KC Hx Discharge Valve IRN291 in " Temp Mode". k /3'tfr6Y-Place the KC Ex Discharge Valve IRN351 in " Mini-Flow Mode". M/'h-16Y3-1RN287A KC Hx 1A Inlet Isol - Open M 7'N-N 1RN347B KC Hx IB Inlet Isol - Open / M/~3-NORN Pump 1A Running Control Room Ventilation System (VC) Y / E N h lign the VC System per OP/1/A/6450/11, Section 3.0 for Train A. Auxiliary Building Ventilation System (VA) - GM8,w\\l6% %Lm r/M usiLv imtv%WCf1Nokf k.O f1'frM TcKa kC M/3-ZEI4.lign th 'll. C.c;u gr CP/0//./f 'J0/02, S ::icn 2.0 vith th: D f;11;n.; ;;ndi.icn; cr en cptions. A-6uxe c7,htrsteA!AL, M / 32Er'hSEnsure that modification specified in Step 8.1 has been installed. k / M 6 M ll filtered and unfiltered exhaust and supply A fans are off. k / -1b O 3 ASP HVAC Unit 1A and 1B are off. m-3 ,,,.,, ~
i; Page 4 of 4 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.3 ALIGN?iENT OF AFFECTED SYSTEMS Boron Recycle System (NB) Qi M/3-18-U Align the hb System for recirculation of RtNST per OP/1/A/6200/12, E:: 1... o.4 with the following conditions or exceptions: CCCM'3 8/h~/ NN NB459 RfNST Pmp Disch To Aux I Bldg Flush Hdr - Closed M/3-29-4 1NB274 RINST Pmp Disch To PRT - Closed $/}-19-bi INB279 RtNST Pep Disch To Fuel Pool - Closed y4 - r (prJ / 2':32 M "'T 'ST Ir.k Cleamd ; M /3-ND INB199 R!N Pu:rp D;sch To NB Evap - Closed M/ 3'Eb'U1WL915 NB Evap Emer Xover Flush Supply - Closed M /3-29-W IWG211 RINST To WG Decay Tanks Drain Pump - Closed k /3 ~lf-Fr 1NV230 R?M Pump Disch To NV Pu=ps - Closed g r::: "::n n::: c r.r->- tW/ "[8 / ' Jo J. j r m.y ::c.m A.. L.Jy, Jua.my rm y ::vium B oud C Offr G 4 ( ~
Pace 1 of 5 CATAk'BA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.4 ELECTRICAL ALIGNMENT 1 ETA-4160V Switchgear ~Brecker No. Name Position 2 Alt. Feeder B/0 IFTA-1 Oper - Open M/3 28 3 Normal Incoming Oper - Closed % %7. fir 8Y 4 Alternate Incoming No Bkr in Cubicle M/ 9-/Jr8$ 5 1ETXA Feeder Oper - Closed' M/ 3-29 'f'f-6 KC Pump 1A1 Oper - Closed /2/7/ 3-28'bI 7 KC Pump IA2 Oper - Closed M/ 3-7.6U S NS Pump 1A Test - Closed //tf~/'h-28U 9 ND Pump 1A Test - Closed %/M-04 10 1ETXE Feeder Oper - Closed MhtO-65 11 NI Pump 1A Test - Closed / b2NY 12 NV Pump 1A Oper - Closed ((/MN k/ 11 13 CA Pump 1A Oper - Closed 14 RN Pump 1A Oper - Closed k/ ~}-L9-M M/3-M', 15 KF Pump 1A Test - Closed 16 IETXC Feeder Oper - Closed /2 h 3-19 55 17 A/C Compressor A Oper - Closed K / 3-2 % ')- 18 DGIA Oper - Open M/ 34%9-e
s Page 2 of 5 CATAWBA NUCLEAR STATION 1-D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST
- 4 TP/1/A/1350/25A ENCLOSURE 13.4 C
ELECTRICAL ALIGN!!ENT IELXA - 600Y Load Center Breaker No. Name Position [ 8 3-EB 4 1 4B Normal Incoming Oper - Closed / + 4C IE!!XA Feeder Oper - Closed g/349-t5 4D Not Used .5A 1E!!XC Feeder Oper - Closed M /FEb64 SB 1E!!XG Feeder Oper - Closed SF/MM9 SC Not Used SD Not Used 6C IE!!XE Feeder Oper - Closed $34Mi 6D Not Used 6B Alternate Incoming Oper - Open [A~/3 M i IELXC,- 600V Load Center Breaker No. Name Position 4B NormaJ Incoming Oper - Closed [/MM gy[ 4C 1E!!XI Feeder Oper - Closed M/ 3-19M ,e 4D Not Used SC IE!!XK Feeder Oper - Closed g/ SD Not Used i 5B Alt. Incoming i Oper - Open ((/3" b i 4 ~
Page 3 of 5 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.4-ELECTRICAL ALIGNMEhT 600V - Essential and Blackout Motor Control Centers NOTE: .The maximum number of breakers possible on the following 600V MCC are to be closed. Incoming breaker should be closed and MCC energized. MCC Number I F 3-29's4-IEMXA / / 1EMXC K / ~3-2b61 6/ b'N 3 IEMXE N 3-lM 1EMXG / % / 3-thf'f-1EMX1 h / b-L@% 1EMXK 1EMXO [ / 'p 2.9 8 9 IEMXQ N/ 3-2.E'N ff/ '}-LG-N 1EMXS IMXO kJ / 3'N'k-@ IMXQ MJ / S.2S-f,6 ItDN 8 / Sd44 120 VAC/125 VDC Vital Power NOTE: The maximum number of circuit breakers possible on the following 120 VAC/125 VDC essential, vital and blackout instrument and control power panelboards and distribution centers are to be closed. Pane 1 boards and distribution controls should be energized. Power Pane 1 board No. k/ 'NU 3 1EKPE IEKPG f / Sf FN
Page 4 of 5 ^ CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.4 ELECTRICAL ALIGNMEhT Power Panelboard No. [/@ZO bY IEKPI IEKPY [/3-2SO 1 EDA Q"/3-1864 1EDC [/34SO Kp-2.GM 1DGDA h7MM4 1ERPA A/ f'T3-1Bii IERPC ICDA N /.}29-M IKPW $/.5-?iilO Unit 2 Breakers 2 ETA Breaker No. 14 Test-Open 8/ -N 3 IFTA - 4160V Switchgear Breaker No. Name Position 1GTA1 Swgr IFTA Norm Inc Bkr Oper - Closed,6 /3"dN IFTA1 Swgr IFTA Alt Inc Bkr Oper - Open N/MM 1FTA2 Spare / -Z96 3 IPA 3 XFMR ILNI Tdr Bkr Oper - Closed l l l
Page 5 of 5 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.4 ELECTRICAL ALIGNMENT ILXI - 600V Load Center Breaker No. Name Position 4B Inc Bkr Oper - Closed M' / 3-d'fM-4C MCC IMXO Tdr Bkr Oper - Closed - Auto W / }2&N4 SA VI Comp A Oper - In Base M/ 3-26 61 SB HCC IMXQ Fdr Bkr Oper - Closed - Auto f6 /3-tS-b4 SC MCC IMXW Tdr Bkr Oper - Closed - Auto R /b2944 jl247 / Mi 3 SD ICCA Tdr Bkr Oper - Closed 6A Spare 6B Spare 6C PZR Her Pwr Pn1 1A Open /MMD 6D Spare 4 9 e t l
s, Page 1 nr 3 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.S EQUIPMENT OPERATION Load Group 1 1ELXA Compt 44B - Closed / '546"6'f-1ELXC Compt #4B - Closed T / 'N' 3 Boric Acid Transfer Pump 1A - ON N / }46 6 f Aux Bldg Pump Room Heater-Demister - ON M/'3/2 fry 37 Aux Bldg Filtered Exhaust Fan - ON A93/ /n/g9 Switchgear Room Air Handling Units ISGR-AHU-1 ON 7/14/g/zs/ft is/6+'Y W h / 9/4dY 7,/SGR-AHU-/l-ON ISGR-AHU ON At,6/.5/ukv r&r M e '2./SGR-AHU-/ y - ON thrf/q/14/ff VF Filter Train Moisture Eliminator Heater - ON " /59/3,/zs/Py VT Filter Train Exhaust Fan 1A1 and 1A2 - ON /2fd/.3/r5 fryf Aux Shutdown Panel A/C Unit 1A - ON [_/hf~/ F2 8 RN{e"ap Structure Vent Fan IA - ONo 2wp-reze raan liz fr (e{w+,y g,tpg,,,,y I }4IO m r / t, mw) /@d/.9/.L;//*/ D/G 1A Bldg Vent Fan Motors IA1, IA2 - ON Control Room Air Handling Unit A - ON .. /do/3,/ar4r Control Room Area Filter Train Pressure Fan A - ON at/ 3 Control Room Area Moisture Separator Heater A - ON ~ /Jf6 / (9 c>Qs vua. wwA, unA, nces2an tea us - ceen prjue4+ Load Group 2 Centrifugal Charging Pump 1A - ON 84/gy e - - ~ -
s E" "3 W CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.5 EQUIPl!ENT OPERATION ' Load Group 3 /gg' /5-28-F CRDM Vent Fan CRDF-1A - ON CRDF-1C - ON //T / S-19-69 Lower Containment Vent Unit LCVU-1A - ON -Low & /52fr6* LCVU-1C - ON -LOto g/fr /9-Eff % C IY* M " pper Containment Vent Unit UCVU-1A - ON /A J ~' [6/ 349W U .h UCVU-1C - ON- /A-~ ~ g/?f /')-29-64 (Agify A hhtW //F/I }/'N [f pgont Pipe Tunnel Booster Fan 1A - ON-LDLV is'\\1.*L Upper Containment Air Return Fan UCAR-1A - ON //h' /'3-26 64 UCAR-1C - ON g/h-- /}-26 Incore Instrument Tunnel Booster Fan 1A - ON //F / S-26-9+ Incore Instrument Room Vent Unit IA - ON-A/Of_M M / 7,20-O'7-B/0 ?!CC I!!XO FDR Bkr ILXI-4C - CLOSED ((f / >-26-9+ /34f / -ZF-8f 3 B/0 ?!CC lt!XQ FDR Bkr ILXI-5B - CLOSED Load Group 6 Component Cooling Pumps 1A1 and 1A2 - ON N /32 @ Load Group 7 Nuclear Service Water Pump 1A - ON j6h~ / 34&% d g Nuclear Service Water Pump 2A - Breaker 2 ETA-1 is Closed in f./ Test Position 1/Wify /kNfGM /M'O Load Group 8 Aux Feedwater Pump flotor IA - ON k / 349'64 Load Group 10 Reactor ?!akeup Water Pump 1A Id'/rf/ /C A#dW i A/ IT ' k/ F20'h4-g;'g
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ncz. rz.a ::= = / B/0 ?!CC lt!XW FDR Bkr ILXI-5C - CLOSED [/t7 / 946-@ sq iC g czn,i,;;3 rin ;; n;; t7,. y;;3;;; - cy j glf g Fire "retectier hehg Purp "eter * - OP / n-c -n -w 2
Page 3 cf 3 CATAWBA NUCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.5 EQUIPMENT OPERATION Load Group 11 Control Room Area Air Handling Unit A - ON ff/'N 3 Control Room Chilled Water Pump A - ON M / 'E 3 Control Room Chiller Compress Oil Pump A - ON d / F16'98 Battery Room Exhaust Fan - ON [M /'PL9-$i Load Group 12 Control Room Area Chiller A - ON /519-68 Load Group 13 Instrument Air Compressor A - ON N /S2964 Instrument Air Dryer A - DEPRESS ON [/'f / EL6^@ JM r lusui -uus Ali Diyuu C -DEPRESS ON-- / Battery Charger ICCA - CLOSE FEEDER ILNI COMPT SD [6/3-ze&9 Ed Uh,, z au u...- ... fn)iD /but~;6'a i cs ., WS su.rud. F n / r wc > ^ !p Q avva.. y..rua uu vi,..,' <, r. -,,p..v i :..'.)
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CATAWBA hTCLEAR STATION D/G 1A B/0 AND LOAD REJECTION PREOPERATIONAL TEST TP/1/A/1350/25A ENCLOSURE 13.10 EVENT RECORDER ACTUATION TIMES & D/G LOAD VALUES Event Recorder Actuation Sten Point Time 12.1.26 IER282 /fgM/ 907 1ER284 /Sh 6/ 202 9.6/ I W Time Difference Between 1ER282 & 1ER284 lC 8)E Seconds Data Recorded By OM CoF5 Date 9-29-9 4 Calculation Performed By Al Mr3 bNbi Date Step Parameter Value Initial /Date 12.1.20.2 D/G Load (A0574) h,I3 W fg./ $>2PM (Auto-Connected) 12.4.2 D/G Load (A0574) be N tN $/ SMf (Partial Load Rejection) 12.5.2 D/G Load (A0574) 7 09 ru F/ s-x-s+ (Full Load Rejection) 0!I /f. f.4, 2 p/5 4cdo (,' ads 7'9) MtA/ b Ad g,-av an) i e
1 l DUKE POWER GodmtNY P.O. HOX 33180 i CIIAHLOT1*E, N.C. 28242 l IIALH. TUCKER ten.E PHONE ) . 22.""C-June 5, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
My letter of April 18, 1984 provided a response to Catawba SER Confirmatory Item 37, Load Sequencer Accelerated Sequence. Attached for use by the Staff is a copy of TP/1/A/1350/25A-D/F 1A Blackout and Load Rejection Test. Very truly yours, l///(/ Hal B. Tucker ROS/php Attachment cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq. Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environnental Study Group 7 ,f4 i 854 Henley Place / yp Charlotte, North Carolina 28207 !j I}}