ML20151K104

Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test

ML20151K104
Person / Time
Site:	Rancho Seco
Issue date:	07/28/1988
From:	Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
References
AGM-NPP-88-432, STP.668, NUDOCS 8808030126
Download: ML20151K104 (40)

Text

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INDE"ENDENT PROCEDURE REv:EW NOi!CE

. s DATE #R OC E DUT:E NUMBER REV y 07-21-88 STP.668 0 7 g kev!EW[UEM[ #

j EFIC HIGH/ MEDIUM DECAY HEAT TEST p;;0CEDUPE WRITER DEPARTMENT PLANT PERFORMANCE REASON FOR REVIEW:

@ NEW PROCEDURE O nsvrSED PROCEDURE O PTCN g O erEsNiAL aEviEw O SPECiAt Review O PICN O vol0 PROCEDURE O OTHER O PCN atvIENER cowcuRatNet taNC Rto To: DEPT NAmt l MAIL STOP SicNAIUnt/0 Aft TEs No

@ LIC LIC' VERIFICATION .

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@ *RIC RECORDS MANACEMENT 224 I cPROC OA PROCEDURE DEVELOPEMENT 01 R.E C T OR, , NUCLE,AR QUALI.TY 22-107 271

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O N00 M AN AG ER, NOD I F I C A T,I ON S ,291 O MAINT MANAGER, MAINTENANCE 253 E NUC ENG MANAGER, NUCLEAR ENGINEER!NC ,298-6

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E P PERF MANAGER, PLANT PERF.ORNANCE 258 M '

O SOM MCR,SCHED & OUTAGE MCMT 252 O IMS MCR, .INF0 MGMT SYSTEMS 261 O CC&oS NCR, COST CTL L OFF SVCS 270 O

OPS RAD PRO MANAGER, OPERATIONS MANAGER, RAD PRorECTION 255 244

[ .7 g .g O ENVIR MANAGER,ENVIR PROTECT.10N 292A O MAT cNit MANAGER, MATERIAL CONTROL 279 O SRTP ,0! RECTOR,SYS REV & TEST PROC, ,259 O TRNG MANAGER, TRAINING 296 O CHEM MANAGER, CHEMISTRY 250 O SEC {

. SECURITY 210 B (fb. I . J*?U .c28 Y

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O O esoso30126 eso72s PDR ADOCK 05000312 O ,

P PDC e PROCEDURES DEVELOPED IN ACCORDANCE WITH AP.2.19 OR RCAP-0502 g h

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DISTRIBUTION APPROVED DATE d

[/ DE PUl f ME N T / O l v l S 4 0N MANAGER ADM-tee REV 4

PROCEDURE REVIEW COMMENT SHEET

• deoctovatNunsEm STP.668 , 0 m , _M-2 W

. 'f 17 t. E - EFIC HIGH/ MEDIUM DECAY HEAT TEST COMMENT /0ISCARPANCY q[301,yf]OM we. sacitow COMMENTS ACCEPT N01 4CCEPT

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.... ....-... . . - . . . . . . . . - - . . . . . . . . 1 CSVICWED ev: DATE: RCt0Lvt0 av: QATE:

CEVIEWERS SU?ERVISom: DATE: _ APPROVCD BY!

tse r e gwe r ed a QAT(;

e ADM-OD4.1 PEY t e

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PROCEDURE REVIEW CHECXI.IST Written Correctness Procedure No. STP bb8 Rev. O ITEM YES NO N/A

.1 Does each page provide the following identification information?

.1 Procedure number and/or title N

.2 Revision number N

.3 Page number N

.2 Is the format in accordance with administrative procedures? -N

.3 Is the procedure complete and without. any outstanding temporary changes? N

.4 Are the titles and numbers of all referenced documents identified correctly? N

.5' Are graphs, charts, tables, and data sheets adequate for readability and interpolation or extraction of values'

.6 Are instruction steps constructed to comply with the following: ,

.1 Steps deal with only one idea. N

.2 Sentences are short and ' simple. M

.3 User actions are specifically stated. .N

.4 Objects of operate.r actions are l specifically stat 6d. x1 l

.5 00jects of user actions are adequately l stated. N

.6 If there are three or more objects, they are listed (and space is provided for user checkoff).

A0M-0006 Rev 2 Pace 1 of 7

PROCEDURE REVIEW CHECXLIST Written Correctness (Continued)

ITEM YES NO N/A

.6 .7 Punctuation and capitalization are proper. N

.8 Abbreviations are correct and understandable to the user. N

.7 To the best of reflect the as your knowledge, does the procedure N built condition of the unit? _ __

.8 Are worksheets designed to facilitate required computations?

.9 Does the procedure (or related data sheets or worksheets) provide for the independent

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verification and sign-off of computations? N

.10 Plant Specific Nomenclature

.1 Are the acronyms used in accordance with AP.2.10 and understood by the users? N _____

.2 Is the name of the equipment the name usually used by plant personnel?

\

.3 Components, are they identifi,ed by the noun name and equipment' number?

Procedural Accuracy ITEM YES NO N/A

.1 Are the following criteria met?

.1 Can the procedure be performed in the sequence it is written? N

.2 Can the user locate and identify all equipment referred to in the instructions? h ACM-0006 Rev 2 ~

1 Pace 2 of 7

.. PROCEDURE RIVfEW CHECXLIST l

Procedural Accuracy (Continued) I ITEM YES NO N/A

.1 .3 Can the user perform the procedure without obtaining additional information from person (

or documents? N

.4 Can the user perform the procedure without obtaining direct asaistance from persons not specified by the procedure?

.5 Where blanks are provided in the procedure for recording data, does the procedure clearly identify what data (including units, if appli-cable) are to be placed in blank? (initial valve position, instruments reading, etc.) k_i_

.6 Are notes and cautions placed in the body of the procedure before the step for which N they are applicable? N

.7 Are notes and cautions free of action steps?  %

.8 Are. optional steps clearly identified as such? \1 3

.2 Is the amount and level of information (level .of detail) provided by the procedure adequate for N )

the intended use? N

.3 Procedure Referencing and Branching _ l

.1 The vendor manual sections used to develop the procedure, including the control number and revision, reference sectionare explicitly of the listed in the K procedure. ,

.2 _ _ , . .

t The most current vendor manual for the safety-related (Class 1) equipment surveilled, maintained, calibrated, or ,

functionally tested by the procedure '

was compared to the procedure being reviewed. N ACH-0006 REV 2 Page 3 of 7

.- PROCEDURE REVIEW CHECKLIST t

Procedural Accuracy (Continued)

ITEM YES NO N/A

.3 .3 The manufacturer's recommendations were incorportted in the procedure, ,

specifically with respect to test methods and data reduction in determining compliance with the acceptance criteria.

.4 Should the vendor recommendation not be adopted, is written I documentation accessible in Records Information explaining why specific recommendations were not used? \N

.5 Do the Referenced and branched procedures identified exist?

.6 Is the use of referencing minimized?

i

.7 Are referencing and branching instructions correctly worded? N )

.1 "go to" (branching) h

.2 "re'for'to" (referencing) b

.8 Do the instruc'tions avoid routing users past important information such as cautions preceding steps? N

.9 Are the exit conditions compatible with the entry conditions of the referenced or branched procedure?

.4 [

Is the level of detail in the procedure adequate for verification and sign-of" of actions? N

.5 l If quantitative acceptance criteria are used, are ~

they stated as a range as opposed to a point value?xN _

ADM-0006 REV 2 ~

Page 4 ot 7

PROCEDURE REVIEW CHECXLIST procedural Accuraev (Continued)  !

ITEM YES NO N/A

.6 If items (valves, breakers, relays, solenoids, i 1

jumpers, fuses, switches) require alignment to perform the procedure, do the alignment instructions in the procedure meet the following criteria? ,

.1  !

Is each item requiring alignment  !

individually specified?

h j

.2 Is each item identified with a unique number or nomenclature?

N i

\_ L.

.3 Is the position in which the item is to be placed specified?

1

.4 Is the position in which the l' tem is placed verified by sign-off when applicable? \

.5 Does the procedure have specific steps which restore the equipment / system to its normal configuration? y

.7 Are lineups, as given in the procedure, adequato i and are valve / switch positions correct? \ )

.8 If any followup action, test, or procedure must be performed upon the completion of this procedure, does the proc'edure instruct the user regarding what followup action is required and whom to notify?

.9 Does the procedure prohibit isolation or defeat of redundant safety systems when required to be operable? N.N

.10 Does the procedure provide sign-off steps for c first and second checks of affected component position when returning safety-related systems ,

to service?

\

.11 Does the procedure require the Shift Supervisor / '

Asst. Shift Supervisor permission prior to defeating or testing of safety systems?

ACM-0006 REV 2 Page 5 of 7

PROCEDURE REVfEW CHECXLIST procedural Accuracy (Continued)

ITEM YES NO N/A i

l .12 Does the procedure require communications between l

the control room and local operating stations to '

be established and maintained during testing or

operation of equipment that affects control room instrumentation or alarms? x N

.13 For those surveillance or other type procedures that require removing a safety system from service, ,

does the procedure require operability verification of redundant safety system trains after removing the trains to be tested from service? \

.14 For surveillance procedures, does the procedure contain provisions for checking indicatof lights and require replacement of burned out buibt? N

.15 For surveillance procedures, is there a setbs4 for documenting calibration of all instrueents used in the procedure to verify operability of the equipment being tested? s. l l

-N

.16 Are computations required by the procedure based on technically accurate, complete, and current formulas ?

.17 Are computer programs used for calculations callede.fer by the procedure "controlled" per AP.527

.18

.N Have licensing commitments, technical specifica- '

tions, or operating restrictions based on other agreements been incorporated into the procedure? .

.19 Do instruments specified in the procedure to bc used for monitoring operating parameters or for obtaining data meet the following criteria? -

.1 Is the instrument's range adequate for all modes of equipment / system operation? N

.2 Is the instrument's scale or readout calibrated in logical units? N ADH-0006 REV 2 "

Pace G of 7

I r

PROCEDURE REVIEW CHECXL U Procedural Accuracy (Continued) l ITEM YES NO N/A

.19 .3 Are thebyinstrument's required the procedure? Units th6 same as those\ [

.4 Is the scale / readout resolution adequate for determination of specified parameters? _N

.5 Is the instrument specified the proper x, instrument for the desired task? .. V

.20 Where personnel have actions specified in the procedure:

.1 Are the correct personnel specified?

.2 Are reporting chains of commarid or authorities specified correctly? \

.3 Are the instructions adequately detailed for the renuired task? \

.4 Is the referenced procedure that accomplishes i the desired task adequately detailed for the performance of the task? l I

.5 Are steps for restoration to normal .

configuration present in the procedure?

.6 Is there a location in the procedure for signatures of the individuals performing the actions?

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.21 Are inspection hold points properly locatea? N _

.22 Is each inspection clearly defined and the -.. \

acceptance criteria clearly stated? \

.23 For procedures which perform maintenance:

.1 Are retest requirements clearly defined? \

.2 Are Surveillance Procedures referenced for retest where applicable? x

_N ADM-0006 REV 2 ~

Pace 7 of 7 l

e ._. . . _ _ .

' DCCUMENT NO. . b T P. (o b b REV. . CHANGE NOTICE

• PAGE OF b i 1.0 10CFRSO.S9 APPLICABILITY DETERMINATION The procedure, procedure change, modification, test or experiment being reviewed:

1.1 Yes No Basis forswer:an'N Requires a change to the Technical Specifications?

D.i s ,g-CN boGL's nd  ;

cc:o utce o dnavu. 4t> + he. TeekAtoi hen.I@lxrh6ns AM liam Feedder6 w I B 6 kn numill 'in Rah-d .

v 'i o e.wicu %d A InLk'on and conhel Sys b -L bd4h once Throuc k ham C,mo40ca .

%c&ns 3. 4 cma 3,5 w ed. < a v i ew e d .

(Use continuation sheets as necessary) 1.2 Yes No Results in the information in any Licensing Basis Document being no longer true or iccurate or violates a requirement in any Licensing Basis Document (e.g., major changes to theRad =aste Systems Emergency as 4.14).

Plan, see defined in Tech. Spec 6.17, changes to the USAR, or changes to

( Permanent or Temporary)

Basis for answer: D t. bklos net . %ecbbfd O hG O h b d v)O yO_.

re_\/ ( e w/ ed God no ifn t d - bund i 10 1 ,4,1,2,4.

4,1,2, 2 A .S .4.2 , 9. 2 \ b 2. 2. . 7 . 4 . B . 2. . '

l hdn b,3- .1 C OV2v'% yn Acbv Te o nS')M e4 AF w Tn ', heion and dwbn 4best 'A is i nt >on d ee d .

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1 I

(Use continuation sheets as necessary)

If the answer(See implemented to question Section 5.21.1ofisRSAP-0901).

"YES," A Safety Analysis is required before the activity can be i

• i f action 2.0 of this fern must be completed.the answer to question 1.2 is "YES," then an Unreviewed Safet/ inalysis is rot rCgJifed and an Unreviewed Safety Question Detemin re m rai. Complete itsms 3.0, 4.0, and S.0.

ALM-XO3, Rev. S Sneet 1 of 3

-m. -

10CFR50.59 DETERMINATION D CUMENT NO. hTb, b REV. CHANGE NOTICE PAGE _OF 2.0 UNREVIEWED SAFE 7Y QUESTION DEVERMINATION 2.1 Yes No May the probability of occurrence of an accident previously evaluated in the SAR be increased?

Basis for answer:

(Use continuation sheets as necessary) 2.2 Yes No May the consequences of an accident previously evaluated in the SAR be increased?

l Basis for answer:

l '

(Use continuation sheets as necessary) 2.3 Yes No May the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR be increased?

Basis fea answer:

(Use continuation sheets as necessary) 2.4 Yes No May the consequences of a malfunction of equipment important to safety previously evaluated in the SAR be increased?

Basis for answer:

(Use contint'ation snetts as necessary)

ACM C003, Rev. 5 Sheet 2 of 3 i

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f . CCCUMENT NO. b[ f. b d REY.

f CHANGE NOTICE

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PAGE OF

' 2.5 Yes No May the possibility for an accident of a different type than any l evaluated previously ici the SAR be created?

Basis for answer:

(Use continuation sheets as necessary) 2.6 Yes No May the possibility for a malfunction of a different type than any evaluated in the SAR be created?

Basis for answer:

(Use contiavation sheets as ne;.;sary) 2.7 Yes No IS the margin of safety as defined in the bas'as for any Technical Specification (s) be reduced?

Basis for answer:

(Use continuation sheets as necessary)

If question 1.2 is marked "Yes" and "Permanent" (i.e., a permanent LBD change required) 'a copy of the procedure, annual USARtest or modification shall be forwarded to the Nucitar Licensing Department for inclusion in the update.

If any question is answered "Yes" in Section 2.0, the document being reviewed must be forwarded to the Nuclear Licensing Department for a detailed Safety Analysis before processing is continued.

If all answers forward to the are PRC"No,"a detailad Safety Analysis is not required. Continue processing of document and for review.

3.0 PREPARED BY: DN -

Ah dATE - N N 4.0 REVIEWED BY: 1 " #M DATE [!

5.0 PRC REVIEW:

5.1 50.54(p) SECURITY REVIEW REQUIRED YES ( ) NO 5.2 st.sma :ntaarNCY PR0cRAs REvIE' r Ecu: RED 5.3 IC 3 4 a) rp tITY rs0 GRAM R 'I # I' '

1 YES c 3 NO c, r r , _ YES [ ] N0 pi 5.: A m o/ a rY N C CsAIRrta . ._ 1 _ _3. __ _ -

_ DATE f _ _ , , _

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i STP.668 EFIC HIGyMEDlW DECAY HEAT TEST SECTI N SUBSECTIW TITIE PEiE 1.0 TEST OBTECTIVES 1 2.0 SPECIAL TEST EQUIINENT 1 3.0 m.acQJISITES 2 4.0 INITIAL CCEDITIONS 4 5.0 LIMITS AND PRECAUTICUS 5 6.0 PROCEDURE 6 7.O ACCEPTANCE CRITERIA 10

8.0 REFERENCES

11 9.0 ENCICSURES 13 9.1 Procedure A.51 Excerpt 14 92 IDADS Surveys 20 9.3 Signature / Initials Sheet 23 9.4 Rancho Seco Test Icg 24  :

I 9.5 Test Procedure Authorization Form 25  !

l QUAL.lTY APPRO

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.zw pst Rev. O STP.668 - 1

-_. _ _ _ . = . ._.,

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k STP.668 EFIC HIGH/MEDIU4 EECAY HEAT TEST ,

1.0 TEST OBTECTIVES 1.1 To functicnally demonstrate the operability of the Emergsncy Feedwater Initiaticn ard Control (EFIC) system controls and indication under high/ medium decay heat ecnditions after Auxiliary Feadwater (ATW) initiation.

1.2 To diss-bute stability for the following parameters (under high/ medium decay heat conditions) during EFIC control of AEW:

1.2 .1 Average Reactor Coolant System (RCS) tenperature.

1.2 .2 Pressurizer level.

1.2 .3 APf flow.

1.2 .4 EFIC Once Through Steam Generator (OISG) Isvels.

1.1 .5 OPSG pressures.

2.0 SPECIAL TEST EQUliHDff l 2.1 h, four channel strip chart recorders with DC Voltage input anpiifiers, or equivalent.

l t Rev. O STP.668 - 1

Initialc/Date 3.0 rm2wwiJISITES 3.1 'Ihe w=Lrocticn and G.mycE=Lt testing of ECN A5415, EFIC Mod 1 installation is ocmplete. /

3.2 STP.lll3, EFIC Hot Functional Test is field ocmplete. / _

3.3 'Ihare are no open work requests on the followirq systans which will affect the results of this test:

3.3 .1 Integrated Control System (ICS). /

3.3 .2 Interim Data Acquisition and Display Systen /

(IDADS) .

3.3 .3 Emergency Feedwater Initiation and Control System (EFIC). /

3.3 .4 Feedwater System (INS). /

3.5 .5 Main Steam System (MSS) . /

3.3 .6 Reactor Protection System (RPS). /

3.3 .7 Safety Features Actuation System (SFAS). /

3.3 .8 Safety Parameter Display System (SPDS). /

3.4 'Ihare are no potential deviations frcan quality (PDQs) on the following systems which will affect the results of this test:

3.4 .1 ICS. /

3.4 .2 IDADS. / l 3.4 .3 EFIC. /

3.4 .4 FHS. /

3 4 .5 MSS. /

3.4 .6 RPS. /

3.4 .7 SFAS. / )

3.4 .8 SPOS. /

Rev. 0 l

STP.668 - 2 i l

e ws.mX/JISITES (Continued) Initials /Date 3.5 2ere are no tanporary modification tags in place on the following systems which will affect the results l of this test: )

1 3.5 .1 ICS. /

l 3.5 .2 IIRDS. / j 3.5 .3 EFIC. /

3.5 .4 ENS. / _

3.5 .5 MSS. /

3.5 .6 RPS. /

3.5 .7 SFAS. /

3.5 .8 SPDS. /

3.6 2 ere are no clearance tags in place en the following systems which will affect the performance of this test:

3.6 .1 ICS. /

3.6 .2 IDADS. /

3.6 .3 EFIC. /

3.6 .4 IHS. /

3.6 .5 MSS. /

3.6 .6 RPS. /

3.6 .7 SFAS. / 4 3.6 .8 SPDS. . . . ,

3.10 he plant Chemistry department has been notified of this test performance. /

3.11 A pre-test briefing has been cxn10cted, using the Test l Briefing Checklist, with all test participants. / _

i 3.12 2 e Shift Supervisor has given permission to perform this test by signing the Test Procedure Authorization i Form. / l I

RBV. O STP.668 - 3

'1 p

Initials /Date  ;

4.0 INITIAL ONDITICNS 4.1 h condensata Storage Tank (CET) contains at least .

270,000 gallons as indicated by LI-35803 on HISS. / -

I 4.2 The plant has been operating at approximately 80 percent power for at least four days prior to the reactor trip. /

4.3 The rwactor has tripped and the i msdiata actions i of E.01 and E.02 have been performed. /

i 4.4 The recorders have been installed and the Work Request number has been recorded in the Test I.cg. /

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Rev. 0 l S1'P.068 - 4 1 1

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5.0 LIMrIS AND PIEXWRIONS  !

5.1 The aimiliary feedwater pmp motor start limitations 1

are:

5.1 .1 No more than five starts are allowed in any twenty - four hour period.  !

5.1 .2 If the motor starts frcan ambient temperaturn and runs for not more than two minutes, the notor may be restarted one time following motor coastdown to rest.

5.1 .3 After the motor has been runnire continuously for a mininnn of four hours, it may be stopped, allowed to coast down to rest, and restarted one time.

5.1 .4 Under all circumstances other than 5.1.2 and 5.1.3, the motor must be stopped for a minimum of five hours before another single start is permitted.

5.2 The CST water nust meet the chemistry specifications per the Unit 1 Chemistry Manual R.S.

5.3 Hotwell level shall not exceed 48 inches without Shift Supervisor approval.

5.4 For the followirq valves, do not avraa4 the 5 minute duty cycle or operate more than ten times in any hour:

5.4 .1 HV-20577 AEW Isolation Valve.

5.4 .2 HV-20578 AIW Isolation Valve.

5.4 .3 HV-20581 AYW Isolation Valve.

5.4 .4 HV-20582 AEW Isolation Valve. 1 i

5.5 No more than three reactor coolant pmps may be operated when the reactor coolant tenparature is below 500 degrees Farenheit as indicated cri the wide range taperatum indicator.

l 5.6 Main feedwater shall be reestablished slowly in order to maintain '

stable primary to secondary heat transfer ocnditions.

5.7 The pressurizer shall not be filled above the 290 inch level.

5.8 The minimum allowable pressurizer level is 10 inches.

Rev. O STP.668 - 5

.- . - . . == .. _ .- . - _ _ -. - _.

Initials /Date 6.0 PIOCE[URE M: A Signature / Initials Sheet (Enclosure 9.3) and a Rancho Seco Test Io; ,

(Enclosurs 9.4) shall be maintained by the Test Director during the ocmduct of this test.

6.1 Manual APW Initiation.

M: If the RCS taperature decreases below 510 degrees Farenheit, the control Roca Operator is to take control of the system in order to remain above 500 degrees Farenheit.

CAITTION : No ERE THAN THREE REACIOR COOIANT PUMPS MAY BE OPERATED WHEN THE REACICR COOIANT TEMPERAIURE IS BEIIH 500 IEGREES FARDG2IT AS INDICATED CH THE 1 WIDE RANGE TEMPERATURE INDICAIOR.

6.1 .1 Record the IDADS time for the reactor trip. 1 TIME : / / /

HR MIN SEC M: When the reactor trips, the ICS will

, run MrW back. After each OTSG level i undershoots the low level limit, the i cowsyciding Main Feedwater Startup Valve will begin to refeed. Manual initiation of AFW nust occur at a time A33r Startup Valve refeed for both OISGs and before 5 minutes lapsed time since the reactor trip.

6.1 .2 At panel HISS (E), simultaneously DEPRESS the

' Inft and Right AEW pushbuttons on the EFIC Channel A Initiate / Test Matrix. /

6.1 .3 Record the IDADS time for EFIC Channel A manual initiation of AEW.

TIME / / /

HR MIN SEC Rev. O STP.668 - 6

1 PROCEDURE (Ocotinued) Initials /Date i 6.1 .4 At panel MISS(E), sintiltaneously IEPRESS the l Left arx1 Right AEW pushbuttons on the EFIC Channel B Initiate /1%st Matrix. /

6.1 .5 Record the IDADS time for EFIC Channel B manual I initiation of AEW.

TI!E : / / / I HR MIN SEC I l

6.1 .6 At panel HlRI, place in HAND the following Bailey l Control Stations: i l

6.1 .6.1 Main Fedwater Pump A /

6.1 .6.2 Main Feedwater Pung B /  ;

)

EEE : 'Ihe Shift Supervisor / Assistant Shift )

Supervisor will make the determination  :

that AEW is in service and available l by checking indications en HISS (E) prior to closure of W-20515 and W-20516.

6.1 .7 At panel H1RI, D"PRESS the CISG A MEW ISOIATICH, W-20515 CIOSE BLPB and CHECK the followirxJ at panel HlRI: /

6.1 .7.1 W-20515 OPEN BIP3 is OFF. /

6.1 .7.2 W-20515 CIOSE BLPB is CN. /

6.1 .8 Record the IDADS time for Main Feedwater isolation to A DISG.

TIME : / / / .

HR MIN SEC  !

6.1 .9 At panel HlRI, DEPRIES the CISG B MEW ISOIATION, W-20516 CICSE BIPB ani CHECK the following at panel H1RI: /

6.1 .9.1 W-20516 OPEN BIPB is OFF. /

6.1 .9.2 W-20516 CICSE BLPB is CN. /

6.1 .10 Racerti the IDADS time for Main Feedwater isolation to B OPSG.

TIME : / / /

HR MIN SEC Rev. O STP.668 - 7

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Initials /Dste PROCEDURE (Continued) l 6.1 .11 Ctserve EFIC control of CISG level at approximately l

27.5 inches (LI-20505A and LI-20506A) and record the ItaDS time after at least 20 minutes of EFIC AFW l autmatic control.

/

TIME : / / __

1 HR MIN SEC f

6.1 .12 Transfer fran Auxiliary Feedwater to Main

/

Feedwater per Enclosure 9.1.

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STP.668 - 8 l

PROCEDURE (Ocntinued) Initials /Date 6.2 Restoraticn.

6.2 .1 NOTIFY the Shift Supervisor that the plant testing portion of this test is ocuplete. /

6.2 .2 PDIMM the IDAts surveys per Enclosure 9.2 and attach the survey printouts to this ' d . /

6.2 .3 VERIFY that the ACIUAL MINDiN and MAXDiN values q c, recorded in Enclosure 9.2 are within the ACCEPIANCE nP.

DNELOPE specified. /

6.2 .4 SUBIRACT the time recorded in Step 6.1.1 frcan the y*-

time recorded in step 6.1 .5.

TIME : / / -

TIME : / / =

HR MIN SEC HR MIN SEC (Step 6.1 .5) (Step 6.1.1)

TIME : / / RESUICAIE HR MIN SEC (Step 6.2 .4) /

6.2 .5 VDIFY that the REUIZANT obtained in Step 6.2 .4 Q.C.  ;

is less than 5 minutes. / *P ' '

6.2 .6 Ensure all test participants have signed and initialed the Signature / Initials Sheet, Enclosure 9.3. / .

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I Rev. O STP.668 - 9

7.0 ACCEPIANCE CRITERIA 7.1 Verify, with n=4itun/high decay heat, that EFIC initiation of AEW flw ocotrol will result in adequate but rut excessive cooliry of the Reactor Coolant Systan (RCS). RCS cold leg taperature should be maintained greater than 500 degree.s Fahrenheit. (Step 6.2 .3) 7.2 Follwing a reactor trip, RCS cold leg tenperature, pressurizer level, AEW flw, CESG levels, and CISG pressures will converge and maintain acceptable, post reactor trip values after the EFIC initiation of AEW for a period of twenty minutes. (Steps 6.2 .2 and 6.2 .3) 7.3 Main Feedwater will be isolated to both OISGs within five minutes following the reactor trip to ensure "wiltm/high decay heat is available during the test. (Step 6.2 .5)

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Rev. O STP.668 - 10

8.0 REFERDiCES 8.1 EFIC Systm Status Report, Section 4, Rarv. 2 8.2 ECN DBR A-5415 (Major), Pav. 4, Emergency Feedwater Initiaticn and Control ,

8.3 DxJi neering Support Documents:

)

8.3 .1 Z-EFI-IO146, Rev. 1, EFIC Setpoints & Accuracies  !

8.4 Manuals & Pr vwhtres:

8.4 .1 Technical Specifications, Section 3.1.

8.4 .2 AP.306 III-B, Rev. 4 Unit 1 Chemistry Manual 8.4 .3 A.51, Rev. 35 Auxiliary Feedwater System 8.4 .4 AP.151, Rev. 6, Process Standards OISG Secordary Side {

8.4 .5 AP.152, Fav. 22 Process Standards Feedwater and Condensate Systems i

8.4 .6 B.2, Rev. 47, Plant Heatup and Startup .

8.4 .7 l N 28.02-308, Pav. A, Instruction Manual, Emergency Feedwater '

Initiation ard control System Volume 1 '

8.4 .8 N 28.02-309, Rev. A, Instruction Manual, Emergency Feedwater Initiation and Control System Volume 2 8.4 .9 B&W W a nt 47-1168159-00, Auxiliary / Emergency Feedwater System Review Final Report - Integral System '1% sting, Section 4.3.9.

8.5 Special Test Procedures:

8.5 .1 STP.666, Pav. O, EFIC Cold Functional Test l

8.5 .2 SIP.667, Rev. O, EFIC Cold Functional Preoperational Test 8.5 .3 STP.669, Rev. O, EFIC Time Delay Test 8.5 .4 STP.lll3, Pav.2, EFIC Hot R:rctional %st 8.5 .5 SIP.1154, Pav.0, Remote ShutdchT1 Panel Test Rev. O STP.668 - 11

Vendor Diacrrams Qfr M eel MEGIPTICH 8.6 N 28.02- 1 1 0 AFW SYSITM DESGIPTICH 8.7 N 28.02- 2 1 0 ATW P&I DII.G 8.8 N 28.02- 3 1 0 EFIC CW.ANIZATICH 8.9 N 28.02- 3 2 0 EFIC CRGANIZATICH 8.10 N 28.02- 4 1 2 WIRL I.OGiC OISG 8.11 N 28.02- 5 1 2 EFIC IOGIC OISG A I.EVEL INR7f 8.12 N 28.02- 6 1 1 EFIC I.OGIC OISG B IZVEL INR7f 8.13 N 28.02- 7 1 1 EFIC IOGIC OISG PRESSURE 8.14 N 28.02- 8 1 1 INITIATE IOGIC 8.15 N 28.02- 9 1 1 TRIP IOGIC

, 8.16 N 28.02- 10 1 2 VECICR IOGIC 8.17 N 28.02- 11 1 0 'IRIP TEST PHIIOSOPHY 8.18 N 28.02- 12 1 0 OISG IZVEL SINSING s

8.19 N 28.02- 13 1 1 EFIC S M IOGY  ;

8.20 N 28.02- 50 1 1 SYSTEM BIOCK DIAG (EFIC) 1 8.21 N 28.02- 50 2 1 SYSTEM BLOCK DIAG (EFIC) 8.22 N 28.02- 50 3 1 SYSTEM BIOCK DIAG (EFIC) J i.

8.23 N 28.02- 50 4 1 SYSTEM BICC3C DIAG (EFIC) 4 1

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Rev. 0 STP.668 - 12 l

9.1 Procedure A.51 Dooarpt 1 l

I 9.2 IDADS Survey I 9.3 Signature / Initin1m Sheet 9.4 Rancho Sono Test Icg l 9.5 M Procedure Authorization Fom J

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) Rev. 0 l STP.668 - 13  !

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h ENCIDSURE 9.1 PROCEDURE A.51 .

'IRANSFER FRCH AEW 'IO MFW Step 6,1 .12 M: h Shift Supervisor may N/A ANY steps in Drlosure 9.1.

M: When the 'IF' part of an 'IF. . .'IHEN' statement is not satisfied the step is to be marked N/A.

M: N following Enclosure is to be performed by an Operator.

M: h following is an excerpt frta Procedure A.51, Rev. 35 for the transfer of CTTSG A and B AEW to MFW.

Sign off lines for each step have been aMai for record keeping within this procedure.

7.6 Transfervirn Frte Auxiliary Feedwater to Main Feedwater.

AVtial Conditions:

7.6 .1 AEW has been initiated on HlSSE A and/or B Initiate / Test matrix.

7.6 .2 At least one RCP is running.

7.6 .3 SFAS condition does not exist.

7.6 .4 At least one Main Feed Pump is operable.

7.6 .5 OISG levels are being maintained by AEW at EFIC Inf Isvel Setpoint. (27.5 inches on EFIC Iow Range instruments) 1 DiCIDSURE 9.1 PAGE 1 OF 6 i

Rev. O STP.668 - 14 L

Initials /Date F2fCLOSURE 9.1 (Continued)

A.51 EXCERPr Step 6.1 .12 Procedure:

7.6 .6 For recovery of MEW to the 'A' OPSG, perform the following:

CAITTION : STEPS IN 'IHIS SECTION MJST BE PERFORMED SEQUDTTIAILY OR OISG OVERm.u RESULTING IN EXCESSIVE HEAT TRANSFER MAY RESUIJr.

7.6 .6.1 Place in HAND and run the detands to ZERO on the following Bailey Ctatrol Stations:

7.6 .6.1.1 W-20575, 'A' Startup Feedwater Control Valve. /

7.6 .6.1.2 FV-20525, 'A' Main Feedwater Control Valve. /

7.6 .6.2 Verify CICSED FV-20529, 'A' Main Feedwater Block Valve. / i 7.6 .6.2.1 Verify CLOSED FV-20575, 'A' Startup Feedwater Control Valve. /

7.6 .6.2.2 Verify CICSED FV-20525, 'A' Main Feedwater Cbntrol Valve. /

7.6 .G.3 E the 'SG-A MS"' Trip Lights are lit on either EFIC Initiate / Test Matrix, M Depress ' MANUAL' and ' RESET' for

'SG-A MSL' on the respective Initiate / Test Matrix. /

7.6 .6.4 H the 'SG-A MFW' Trip Lights are lit on either EFIC Initiate / Test Matrix, M Depress ' MANUAL' and ' RESET' for

'SG-A MFW' on the respective 'nitiate/ Test Matrix. /

7.6 .6.5 Check that 'SG-A MSL' ard 'SG-A MFW' Trip Lights are OFF on I!crIH EFIC Initiate / Test Macrices. /

ENCICSURE 9.1 PAGE 2 OF 6 Rev. O STP.668 - 15

,. o Initials /Date DKIOSURE 9.1 (Continued)

A.51 EXCERPP l Step 6.1 .12 7.6 .6.6 Verify a Main Feed Pung in service per l OP A.50, Main Feed Punps System. /

1 7.6 .6.7 Verify OPEN HV-20515, 'A' CfrSG Feedwater '

Isolation Valve. /

7.6 .6.8 Adjust Main Feed Punp speed so that Feedwater Valve p is 50 to 70 paid as indicated on PDI-20567, 'A' Icop Feed Valve p, on HlRI. . /

CAIJrION : MAIN FEEDWATER Si&LL BE REESTARTm{ED SIDWLY IN ORDER TO MAINIAIN STABIE PRD!ARY 70 SECONDARY HEAT TRANSFER CINDITIONS.

M: It may be N ry to raise OrSG level above minim m level setpoint in order to cause the A N control valves to close.

7.6 .6.9 Slowly OFE4 W-20575, 'A' Startup Feedwater Control Valve. /

7.6 .6.10 Maintain Feedwater p at 50 to 70 said, by changing the Main Feed Pump g ad as required. /

7.6 .6.11 Continue with Steps 7.6.6.9 and 7.6.6.10 until W-20527 and W-20531, AW to 'A' OIEG Flow Control Valves, are CICSED. /

7.6 .6.12 M W-20527, AW to 'A' OISG Flow Control Valve is CLOSED, M depress OVERRIDE and CLOSE HV-20581, A W i Block Valve to 'A' OPSG. /

7.6 .6.13 M W-20531, AW to 'A' OTSG Flow Control Valve is CI.OSED, M depress OVERRIDE and CIDSE HV-20577, AN Block Valve to 'A' OISG. /

7.6 .6.14 Place in NJIO W-20575, 'A' Startup Feedwater i control Valve. / l l

7.6 .6.15 Verify 'A' OISG Isvel is being maintained at the l Iow Isvel Limit Setpoint. / l WCIDSURE 9.1 PAGE 3 OF 6 Rev. O STP.668 - 16 I l

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Initials /Date ENCICSURE 9.1 (Continued)

A.51 EXCERPI Step 6.1 .12 1

7.6 .7 For recovery of MEW to the 'B' OTSG, perfom )

the following: '

CATRION : STEPS IN 'IHIS SECTION MUST BE PERFORMED SE2UENTIALLY OR OISG OVERFEED RESULTING IN EXCESSIVE HEAT 'IRANSFER MAY RESUIJr.

7.6 .7.1 11 ace in HAND and run the demands to ZERO on l the following Bailey Control Stations: I 7.6 .7.1.1 W-20576, 'B' Startup Feedwater Control Valve. /

7.6 .7.1.2 W-20526, 'B' Main Feedwater Control Valve. /

7.6 .7.2 Verify CICSED W-20530, 'B' Main Feedwater Block Valve. /

l 7.6 .7.2.1 Verify CICSED W-20576, 'S' Startup i 9'sedwater Control Valve. /

l 7.6 .7.2.2 Verify CU.) SED W-20526, 'B' Main Feedwater Control V?.1.e. /

7.6 .7.3 H the 'SG-B MSL' Trip Lights are lit on either EFIC Initiate /Ibst Matrix, 1 M Depress ' MANUAL' and ' RESET' for

'SG-B MSL' on the respective Initiate / Test Matrix. /

7.6 .7.4 H the 'SG-B MEW' Trip Lights are lit on either EFIC Initiate / Test Matrix, M Depress ' MANUAL' and ' RESET' for

'SG-B MFW' on the respective Initiate /Ibst Matrix. /

7.6 .7.5 Check that 'SG-B MSL' and 'SG-B MEW' Trip Lights are OFF on BOIH EFIC Initiate / Test Matrices. /

ENCIf6URE 9.1 PAGE 4 OF 6 Rev. O STP.668 - 17

Initials / Ente 1

DiCIDSL~AE 9.1 (Continued) i A.51 EXCCRPT .

Step 6.1 .12 7.6 .7.6 Verify a Main Feed Punp in service per OP A.50, Main Feed Pumps System. / __

7.6 .7.7 Verify OPEN HV-20516, 'B' OTSG Feedwater Isolation Valve. /

7.6 .7.8 Adjust Main Feed Pump speed so that Feechrater Valve p is 50 to 70 psid as indicated on PDI-20568, 'B' Icop Feed Valve p, on H1RI. __

/

CAUTION : MAIN FEEDWATER SHAIL BE REEoM SIDWLY IN ORDER TO MAINTAIN STABIE PRIMARY TO SECDNDARY HEAT TRANSFER OCtIDITIO!E.

M: It may be m " w y to raise OTSG level ,

above minimum level setpoint in order to  :

cause the AEW control valves to close.  !

7.6 .7.9 Slowly OPEN FV-20576, 'B' Startup Feedwater Cbntrol Valve. /

i 7.6 .7.10 Maintain Feedwater p at 50 to 70 psid, by j changing the Main Feed Pump speed as required. /

l 7.6 .7.11 Continue with Steps 7.6.7.9 and -*.6.7.10 until W 00528 and EV-20532, AEW to 'B' OISG Flow Con-cl Valves, are CIOSED. /

l 7.6 .7.12 M W-20528, AFW to 'B' OI?G Flow Control Valve is CIOSED, M deprns OVERRIDE and CIA'E HV-20578, AIW Block Valve to 'B' OISG. /

7.6 .7.13 M FV-20532, AFW to 'B' OISG Flow Control Valve is CIOSED, M depress OVERRIDE and C W E HV-20582, AEW Block Valve to 'B' OISG. / _

7.6 .7.14 Place in AUIO EV-20576, 'B' Startup Feedwater control Valve. /

DiCICSURE 9.1 PAGE 5 OF 6 Rev. O STP.668 - 18

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IDitials/Date DiCICSURE 9.1 (Ccs1tirmed)

A.51 EXCERPP Stap 6.1 .12 7.6 .7.15 Verify 'B' CTTSG Isvel is beiry maintained at the  ;

Im Isvel Limit Setpoint. / .

7.6 .8 Depress MANUAL and RESET for 'AFW' on the 'A' Initiate / Test Matrix. /

7.6 .9 STOP P.-319, Auxiliary Feedwater Pump. /

7.6 .10 Depress MANUAL and RESET for 'AEW' on the 'B' Initiate / Test Matrix. /

7.6 .11 STOP P-318, Auxiliary Feedwater Punp. /

7.6 .12 Depress the EFIC A Control Initiate BLPB. /

7.6 .13 Verify the EFIC A Control Initiate BLPB is OFF. /

7.6 .14 Depress the EFIC B Control Initiate BLPB. /

7.6 .15 Verify the EFIC B Control Initiate BLPB is OFF. /

I DiCIOSURE 9.1 PAGE 6 OF 6 Rev. O STP.668 - 19

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ENCIOSURE 9.2 IDADS SURVEYS j STEP 6.2 .2 i 9.2 .1 Perform the IDADs surveys for the points listed in Steps gg, 9.2 .1 and 9.2 .2 for the following time interval. gP.

E 1B21 TIME : / / TDE : / /

HR MIN SEC HR MIN SEC (Step 6.1 .3) (Step 6.1 .5 + 20 minutes)

ANAI.OG ID08 RC PRESSURIZER LVL 1 DP (IN)

ID09 RC PRESSURIZER LVL 2 DP (IN)

P9035 RCS PRES ICOP A P9036 RCS PRES IDOP B T016 BC LP B CDID IIG TD(P - WIDE RNG l T017 RC LP A 00ID IB3 TD{P - WIDE RNG ID39 SP OISG A SU RNG LVL (INH 2O)

ID40 SP OISG B SU RNG LVL (INH 2O)

IB811 EFIC G A SG-A 10 RANGE IIVEL (INGES)

L9812 EFIC CH B SG-B 10 RANGE LEVEL (INGES)

Use the Digital points listed in 9.2.2 as a mask.

/

Ccanpleted By Date ENCIOSURE 9.2 PAGE 1 OF 3 Rev. O STP.668 - 20

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I l ENCICSURE 9.2 (Contiraled) l IDADS SURVEYS STEP 6.2 .2 9.2 .2 Analog ard digital mask points. '

l AE2M 9 P800 SP OISG B OUIIEF SIEAM PRESS P801 SP OISG A CUTIEF STEAM PRESS P9801 EFIC G A SG-A PRESSURE P9802 EFIC G B SG-B PRESSURE F9600 MI;7 FIIM B E9601 MFW FIfW A F9660 ATW FIfM TO OISG A FT-31802 (GIH)

F9661 AEW FIIM 'IO OISG A FT-31803 (GMf)

F9662 ATW FIIM TO OISG B FT-31902 F5663 AEW FIfW TO OISG B ET-31903 DIGITAL G1600 ATW INITIATE 1B G1601 AEW INITIATE 1A G1602 ATW INITIATE 2B G1603 AEW INITIATE 2A G6599 MANUAL REACIOR TRIP

/

Cw yleted By Date DiCI.OSURE 9.2 PAGE 2 OF 3 Rev. O S T.668 - 21

a ENCIOSURE 9.2 (Cdntinued)

IDAE6 SURVEYS STEP 6.2 .3 9.2 .4 Review the IDADS data obtained in Steps 9.2 .1 and 9.2 .2 for the o.c.

time period listed in 9.2 .2 to ocanplete the following (pressures H.P. l are psig and temperatures are degrees Farenheit):

ACCEPTANCE DNEIOPE ACIUAL  ;

l PODTP ; DESCRIFFIONl, MININUM MAXDEN l MINIEM MAXDEM l t I l l IDos l PZR LEVEL l 10" 290" l l r9c y I t 1 L l1009 l PZR LEVEL l 10" l 290" l l fl lE9035 l RCS PRESS l 1700# l 2400#

l l fP9036 l RCS PRESS l 1700#l2400# l i i i i i i l T016 l T CDID B l 510F l 560F l l (,.

i i i e i i l T017 l T COID A l 510F l 560F l l --

i i i i i i l 1039 l SU LVL A l 20" l 50" l l lID40 l SU LVL B l 20" l 50" l L l IS811 l EFIC IO A l 23" 4 I I l55" i

l e

l i

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l IS812 l EFIC 10 B l 23" l, 55" l i

i i e i l,

i l W l P800 l OISG B PRES l 965# l <1020# l l l l 1 l  !  !

i l

l P801 l CTPSG A ERESl 965# l <1020# l l h"g, n 1 - l  !  ! i l P9801 l EFIC A P il 965# l <1020# l l l ,

g c; i i -i  ! l  ; -

l F9802 l EFIC B PRES l 965# l <1020# l l l M

l E9600 MEW FICW B l N/A N/A l l {l l E9601 l MEW FICH A l N/A l N/A l l I i i l

i

{

i l E9660 l AEW FILM A l N/A l 940 GEM l l l , .-

l  ;  ;  ; '

I F9661 l AFW FIfW A l N/A l 940GPM l l l y,gh7 i i i i i .

l F9662 l' AEW FIfW B l N/A l 940 GEM l' l l l  !  ;

{ ' 'o 'c.

F9663 N/A l l AEW FIfW B l l 940 GEM l l {

INSPECT ENCIOSURE 9.2 PAGE 3 OF Y Rev. O STP.668 - 22

.. 3 1

DKIOSURE 9.3 SIGGGURE/INITIAIS EGEr l

M (PRETED) SIGNAIURE m

)

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MCICSURE 9.3 PAGE _ OF_

Rev. o STP.668 - 23

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ENCLOSURE 9.4 l Date

'1%st Number STP.668 ,

Page of RANO O SECO TEST IOG TIE #l DATE l TIME l RDDGKS l l l l l l l l 1 l l l 1 l l l I I l l l l ..l I l i  !

I I I I I I l l l l l 1 I I l 1 I I I i I l l l l l 1 I I l l l l 1 l 1 l 1 i l l I l l l I l 1  !

I I I I I I I l l 1 l l I I I I I l l I I l l l l l l l 1

1 I l l l l l 1 I I l l 1 1 I I I I l

ENCICSURE 9.4 PAGE 1 OF 1 Pav. O STP.668 - 24 l

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F e

ENCLOSURE 9.5 Tff*f PROCEDURE Atm ORIZATICH EORM TEST PROCEDURE NUMBER _ _ . STP.668 REVISICti 0 TITLE EFIC HIGH/ MEDIUM DECAY HEAT TEST ym.;nsi REVIER CO!PIETE /

TEST DDLTIOR MIE RELEASED FOR yt40ie9ECE /

SRIP DwFflOR DATE AUIHORIZATION 'IO ODt00CT TEST /

SRIP ASST DIRECIOR DATE

/

OPERATIONS SHIFT SUPERVISOR DATE

• TEST FtMOle!ANCE CmPIEIE /

TEST DIRECIOR DUE

• READY IOR RESULTS REVIEN /

SRTP ASST DIRECIOR DATE

• INDICATES TESTING CMPIfrE AND ACCEPIANCE CRITERIA HAS BEEN SATISFIED.

ENCLOSURE 9.5 PAGE 1 OF 1 Rev. O STP.668 - 25

C-A f

J (Dsuun SACRAMENTO Mull!CIPAL UTluTY DISTRICT C 6201 S Street, P.O. Box 15830, Sacramento CA 958521830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA l

l AGM/NPP 88-432 1

OUL 2 81998 U.S. Nuclear Regulatory Commission Attn: Dennis M. Crutchfield, Director Division of Reactor Projects Mail Station Pl-137 Washington, D.C. 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 EMERGENCY FEEDWATER INITIATION AND CONTROL SYSTEM TESTING

Dear Mr. Crutchfield:

Attached is test procedure STP.668, EFIC Medium /High Decay Heat Test. A preliminary Test Outline was forwarded to you by letter CEO G8-112, dated July 22, 1988.

If you should have any questions or require additional informa-tion, please contact me at (209) 333-2935, extension 4741.

Sincerely, I,wt K 15wa~

an R. Keuter (pAssistantGeneralManager, l 1

Nuclear Power Production  !

Attachment cc: A. D'Angelo, NRC, Rancho Seco G. Kalman, NRC, Bethesda J.B. Martin, NRC, Walnut Creek l

' \

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RANCHO SECO NUCLEAR GENERATING STATION D 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935 l

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o SPECIAL TES

T. PROCEDURE

REQUEST / APPROVAL FORM g,

SECTION 1. 0 AC T IOtti. - ( I) New Procedure -( ) Procedure Revlolon Special Test " r Procedure No. E*M '

Rev: O ritien EFIC HIGH/MEDIIM DECAY HEAT TEST .

O,i,in...r: larry Wittruo T Cthm, ( M 7 / 25 / 9]D H Recuented chanoe: -

M L1J D

C U Reason for change!

E eo,.4: *yfy.;4soi.Mio.,

NU/[N o t.:Y((///^ [ A44-r

- oir, sire .r M,c, riant re> f.

o.te: 2/ K noe. end Approves av etant Review c. ittee: Yee No O S.

+

SECTION 4. MMENDATION APPR VAL YES ( ) N0 f n ov i e.e d:

M<) a ~ v w>r oate:Yb ~

J R e c oreme n d w by Management Safety view Co.eisstee: ( ) YES (A NO

<C y SECTION 5.0 MSRC REVIEW ( ) N/A O Authorization to Forward to MsRC: oate:

g MSRC Review:

ia,,r...i avin.ri.,>

Date:

CL inen.,..... s.r..,n..... c. .....>

CL

.g GECTION 6.0 FINAL APPROVAL l M Date: 7 (olrector, Nuclear Operatione and Maintenance) d Approved: Date:

<( J' Test Coordinator Q "...-

g Approved: Date: Date:

Group Supervisor o ir, simp er Mgr, riant P er f.

g Approved: Date:

Plant Revne. Convaitsee R e c onwne r d R e v i e w by Management Sa fety Review C omus s t s e e : Yes O No O b Approved: Date:

J D ir, Muei.ar op. ration. s Maintenance 3 Forward to Manage ent Sa fety Review C e aun i s t e e : Yee O No D

@ i tij g R..i...  : ('h k/ Det.:

san.....nt sar.ty R.wie, co, itteo ygg ACM-099 REV. 2 \ \