ML20132C711

Provides Supplemental Info to Jg Partlow 850213 Memo Re Plant Operations & Surveillance Program Insp Team Makeup. Names,Badge Numbers & Social Security Numbers of Several IE Personnel Listed

ML20132C711
Person / Time
Site:	San Onofre
Issue date:	02/15/1985
From:	Partlow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20132C709	List: IR 05000206/1985012 IR 05000225/2003005 ML20132C711 ML20132C985 ML20132C996 ML20133Q279 ML20133Q320 ML20133Q337 ML20133Q367 ML20133Q404 ML20133Q423 ML20133Q439 ML20134A015 ML20134A045 ML20134A163 ML20134A252
References
FOIA-85-425 NUDOCS 8502220168
Download: ML20132C711 (1)

Text

.

/pn asetig'o,i UNITED STATES I'

NUCLEAR REGULATORY COMMISSION t-t WASHINGTON, D. C. 20565 a.,.....J Decket No. 50-362 FEB i 51985 4

ME:40RANDUM FOR:

Dennis F. Kirsch, Acting Director Division of Reactor Safety and Projects, Region V FROM:

James G. Partlow. Director Division of Inspection Programs Office of Inspection and Enforcement

SUBJECT:

FLANT OPERATIONS AND SURVE!LLANCE PROGRAM INSPECTIONS BY IE PERSONNEL - SAN ONOFRE UNIT 3 This memorandum is sent with the intent of providing supplernental infomation to the J. G. Particw memorandum to D. F. Kirsch of February 13, 1985.

The c::eplete infomation as to inspection team makeup is as follows:

Name_

Badge No.

Socia _1 Security Number

• Leonard J. Callan A-3052 458-72-8770 Der.nis J. Sullivan, Jr.

A-3304 550-42-0201 Scott A. McNeil A-3476 216-72-2715 James T. Conway A-3075 517-44-8204

• Team Leader

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION h

WASHINGTON, D. C. 20646 s.,...../

Occket No. 50-362 FEB a 51985 MEMORANDLH FOR:

Dennis F. Kirsch, Acting Director Division of Reactor Safety and Projects, Region V FROM:

James G. Partlow, Director Division of Inspection Programs Office of Inspection and Enforcement

SUBJECT:

PLANT OPERATIONS AND SURVEILLANCE PROGRAM INSPECTIONS BY IE PERSONNEL - SAN ONOFRE UNIT 3 This me'ncrandum is sent with the intent of providing supplemental information to the J. G. Partlow remorandum to 0. F. Kirsch of February 13, 1985. The expiete infonnation as to inspection team makeup is as follows:

Name Badge No.

Social Security Number

• Leonard J. Callan A-3052 458-72-8770 Dennis J. Sullivan, Jr.

A-3304 550-42-0201 Scott A. McNeil A-3476 216-72-2715 James T. Conway A-3075 517-44-8204

• Team Leader

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i NUCLEAR GENERATION SITE UNITS 2 AND 3 OPERATING INSTRUCTION 5023-0-35 REVISION 2 PAGE 22 0F 28 ATTACHMENT 4

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PROCEDURE MODIFICATION PERMIT

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NOTE:

This docurrent will be used to authorize procedure modifications and document the appropriate review and approval.

Af fected procedure number %3-r- /.3 Re,. or TCN

//

1.

2.

On page 2 Provide detSils of the modification. Line through all spaces in Section 2.1 that were left blank,.

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Re-evaluation and approval of this permit is required if plant conditions affecting the indicated Step (s) change.

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Does this permit pose an unreviewed safety question per 10 CFR 50.59; 1.e., does it increase the probability of occurrence or the consequences of an accident; create the possibility of a different If yes, then a procedure codification is ny authorized. accident PREPARED BY: _7 cub

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1.0 PREREQUISITES INITIALS /DATE 1.1

-trior to use of an uncontrolled (pink) copy of this Station Document to perform work, verify that it is current by checking a controlled copy and any TCNs or by use of the method described in 50123-VI-0.9

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1.1.1 List any applicable TCNs or write N/A.

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On page 2 Provide details of the modification. Line through all spaces in Section 2.1 that were left blank.

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Re-evaluation and approval of this permit is required if plant conditions affecting the indicated Step (s) change.

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Does this permit pose an unreviewed safety question per 10 CFR 50.59; 1.e., does it increase the probability of occurrence or the consequences of an accident; create the possibility of a different accident; or reduce the Tech. Spec. margin of safety? YES _ N3 g If yes, then a procedure modification is ng authorized.

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1.0 PREREQUISITES

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in Section 2.1 that were lef t blank.

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Re-evaluation and approval of this permit is required if plant conditions affecting the indicated Step (s) changa.

4 Does this permit pose an unreviewed safety question per 10 CFR 50.59 i the consequen;ces.e., does it increase the probability of occurrence or accident; or reduce the Tech. Spec. margin of safety? YESo If yes, then a procedure modification is n_ot, authorized. _ NO $

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w-g NUCLEAR GENERAT?ON SITE UNITS 2 AND 3 OPERATING INSTRUCTION 5023-0-35 REVISION 2 ATTACHMENT 4 PAGE 23 0F 28 PROCEDURE M00!FICATION PERMIT I

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RECEIVCD E 'Y FFH ! F 'e85 AC30 So2/3 Polli A. CROY. P.F.

February 15, 1985 FEB 181925 R. W. KRIEGER R. W. KRIEGER

SUBJECT:

SCE Corrective Action Request (CAR) S023-P-739 Incomplete CPC Addressable Constants Change Log Sheets San Onofre Nuclear Generating Station, Units 2 and 3 Attached is a copy of the subject Corrective Action Request.

This item is considered closed.

f D.

. SCHONE GCLulias:fa Attachment cc:

H. E. Morgan I

P. A. Croy i

L. L. Seyler G. W. Mcdonald F. B. Schmoldt S. D. Endsley B. Turpeau G. C. Lulias V. B. Fisher J. A. Harmon D. B. Schone/ Site QA File R. M. Williams, CAR Coordinator QA Specialist /GO File G. J.

Legner/SOCR QAIS CDMC 2690Q

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d CORRECTIVE ACTION REQUEST S023-P-739 L

2&3 San Onofre Nuclear Gen. Station Unit

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Inccmplete CPC Addressable Constants Change Log Sheets 12/11/84

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Southern California-Edison N/A l

San Onofre Nuclear Generating Station t..

Scn Clemente, California 92672 l

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Operating Instructions S02-3-2.13/S03-3-2.13,' Rev. O, Attachment 8.3, states in part, " Addressable Constants Change Log shall contain all changes past and current, SP.O Operations Supervisor's approval, channel designation, Point 1D, and the latest authorized entered value."

(Continued on Page Two)

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R. W. Krieger/H. E. Morgan 01/31/85

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,et JE Corrective Action Request (CAR) S023-P-739 Page 2 of /f 3 r

BLOCK 6 I

11 Contrary to the above requirements, the following deficiencies were noted:

1.

Log is not always completed as outlined by governing procedures S02-3-2.13/S03-3-2,13.

'.r 2.

Items carried forward are not always identified.

3.

Item not carried forward.(CPC Channel C, Unit 2, Point 1D 062) 4.

SRO Operations Supervisor's initials are missing in several instances, i.e. Unit 3 - CPC Channel D, Point 1D 62 CPC Channel D, Point ID 64 i

CPC Channel A, Point 1D 65 CPC Channel B, Point ID 65 CPC Channel C, Point 1D 65 i

CPC Channel D, Point 1D 65, etc.

i 5.

Pages " carried forward" do not have the corresponding full page I

in t'ae superceded section of the log.

BLOCK 22 J. M. Curran t

P. A. Croy L. L. Seyler-C P. R. King G. W. Mcdonald F. B. Schmoldt C. A. Berg 1

S. D. Endsley

[

i C. A. Olson k

G. C. Lulias V. B. Fisher J. A. Harmon D. B. Schone/ Site QA File R. M. Williams / CAR Coordinator QA Specialist /GO File G. J. Legner/SOCR QAIS I

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SCE CORRECTIVE ACTION REQUEST (CAR) S023-P-739 Page 3 of 3 i

BLOCK 10 The deficiencies noted in Block 6 of the subject CAR have been reviewed.

Item f 4 denotes the absence of SR0 Operations Supervisor's initials on several Core '! Protection Calculator (CPC) Addressable Constants Change Logs.

Operations has determined that the missing signatures did not af fect plant integrity.

BLOCK 11 J a nua ry 31, 1985

_ BLOCK 13 Oversight and the lack of procedural adherence by Operations personnel resulted in the deficiences noted in Block 6.

BLOCK 15 Training will be conducted during pre-shif t briefings reiterating the requirements of Operating I n s truc ti o r.

S02-3-2.13/S03-3-2.13 Calculator Operation.g " Core Protection / Control Element Assembly The subject CAR will be used to provide examples of the deficiencies.

BLOCK 16 March 5,1985 5400u

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-7 Filling and venting of the Unit 3 reactor coola t Instruction 5023-3-1.4).

system (Operating n

lowing refueling (Operator Surveillance TestInte ures system fol-5023 3 3.12).

Specific inspector findings are discussed below g AdsIEis tYa t' ive ' C6fitVoGf 'CErEPHitTct7iWC 9 Constants (Unita)j e

~

The inspector' reviewed Operating Procedure Control Element Assembly Calculator Oper'ation "

503-3 2 13

" Core Protection /

Addressable Constant Logs (one each of the f,

and reviewed the CPC

[

to detemine if adequate administrative controlour CPC channels) for CPC addressable constants.

i The inspector determined that the proced-s we I

ural guidance provided for the administration of the CPC A j Constant Logs appeared to be weak, as evidenced b i

ber of entries that had been lined out and corr ddressable y the significant num-cation as to when the corrections were made or if thected without had received the same level of approval as th the values of the various constants (address blC These e corrected valves a

inputs for the CPC determination of *he De e constants) that are ons personnel to record a

Plant Protection System (PPS). Ratio (DNBR) and Local {

setpoints for use in the stant Logsof Jhe_adminis}1362/_85-A8-A1).g over th upgrading L361L85-0901,rAtive_contro1 8

T b.

Reporting of Plant Chemistry Analysis Result s

1 The inspector identified a concern regarding th 1

reportin i

sonnel g plant chemistry analysis results to on-shif t opera e licensee's method of l

view of ProcedureSpecifically, observations of control room pr

./

50123-111-0.4.4, "Comunicating of Chactices and re-tions as Chemistry Memo", demonstrated that th i

emistry Condi-the inclusion of acceptance criteria (limit )intend e Operations Shift Super-information, such as, previous analysis resultsor without any trending s

Shift Superintendent is not provided the abilit As a result, the judgerent regarding the operationt 1 sig ifi y to make an independent sults, but instead enust rely solely on the recomcance of plant chemistry n

chemistry personnel to initiate corrective measures fomendations istry conditions.

representatives who indicated that their chemistryThis r abnornsi chem-would be reviewed to detemine if the transmission ment reporting practices to the on shif t operations personnel would be of additional data appropriate.

/

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_y UNilS 2 AND 3 REVISION 11 P GE f bh 94 3.0 PREREQUISITES UNIT 2

INITIALS / DATE

(

3.1 Prior to use of an uncontrolled (pink) copy of this Station Document to perform work, verify that it is current by checking a controlled copy and any TCNs;9Q)2 / q/

or by use of the method described in 50123-VI-0.9..

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. 3.1.1 List any applicable TCNs or write none.' ~.,e.;'

f/LJS Ak 3.2 On-Shift SR0 Ops. Supv. approval obtained.

(SRO Ops. Supv. Initials)

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3.3 In order to safely and efficiently start up a unit, equipment deficiencies shall be reviewed to identify impact on the startup and corrective action initiated to minimize the impact. Particular attention must be paid to equipment protective circuits, control schemes

iN."...

and Control Room indications. A careful inspection of control board tags and control system status shall be made. Equipment deficiencies affecting the startup sequence shall be Itsted and the Plant Superintendent, or his designee, shall review the list indicating which Items must be corrected prior to performing the impacted evolution. For example, if the automatic Gland Steam Pressure Regulating System was unavailable, the e

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Superintendent, or his designee, would decide whether the startup should be held pending repair and testing of the Gland Steam System Controls or approve proceeding with the startup using manual control of gland steam pressure. This evaluation of degraded equipment availability should initially be performed in parallel with the verification or performance of system alignments to support startup and re evaluated prior to commencing major evolutions such as heatup, vacuum pull, criticality and turbine roll.

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3.4 The Auxiliary electrical buses are energized.

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3.5 The Plant Protection System is energized and the RPS/ESFAS PZR pressure bypass key locks are in BYPASS.

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3.6 If the RWST level is below 80%, then the RAS has been

. suppressed to prevent loss of shutdown cooling while filling the RCS.

(N/A if RWST >80%)

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3.7 Ensure the Condensate Storage and Transfer System has been aligned per 5023-9-5, Attachment 3 (4),

Condensate StoraDe and Transfer System Alignment.

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hut.LLAR GtNLRA110N SITE UNITS 2 AND 3 OPERATING INSTRUCTION S023-5-1.3 REVISION 11 PAGE 8 0F 94 3.0 PREREQUISITES (Continued)

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INITIALS / DATE 3.8 Er.sure the Demin. Water Storage Facility has been aligned per S023-11-6, Attachment 1. Demin. Water Storage Facility Initial Alignment.

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3.9 Level in the Condensate Storage Tanks is above I. T.S. ' Limits of 97%' for T-121 and above 56% for T-120 M..

I or maleup operattoris are in progress per 5023-9-5.

requirements must be attained for Mode 3 y

3.10 At least 30,000 gallons of capacity exists in the

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radwaste primary tanks to receive radwaste due to unit heatup, or Radwaste Processing is in progress

/j to provide the~ required capacity.

MC / 2/#)P5 The Charging Pu:ap pulsation dampeners are charged

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//

J 3.11 A*J to the pressures stated in S023-3-2.1, Attachment 7, CVCS Pulsation Dampener Operation.

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/ #5 4.0 PRECAUTIONS 4.1 (UNIT 3 ONLY) A RCS heatup of 8*F in any ene hour t

shall not be exceeded when cold leg temperature is

< 110 F.

(This is 2*F more restrictive than

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Ref. 2.1.1, 3.4.8.1.)

4.2 A RCS heatup rate of 25"F in any one hour shall not be exceeded when cold leg temperature is

< 300*F ( 3< 330 F for Unit 3).

{This is 5 F more restrictive than Ref. 2.1.1,3.4.8.1.)

4.3 A RCS heatup of 50*F in any one hour shall not be exceeded when cold leg temperature is above 300*F (330*F forUnit3). (This is 10 F more restrictive than Ref.2.1.1,3.4.8.1.)

4.4 The Pressurizer heatup rate shall not exceed 190*F in any one hour.

(This is 10*F more restrictive than

{

Ref. 2.1.1, 3.4.8.2.)

/

4.5 In Mode 5 with RCS Loops filled, at least one RCP or 50C Pump shall be in operation and one of the

,following additional requirements must be met:

,(References 2.1.1,3.4.1.4.1) 4.5.1 One additto,a1 RCS Loop or SDC Train is operable or 4.5.2 The water level is > 50% WR in each S.G.

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UNITS 2 AND 3 jMi"3j6[3j~~ ~ [{y,))[94 4.0 PRECAUTIONS (Continued)

(\\

4.6 In Mode 4, a RCP or SDC Pump shall be operating and a second RCP/ Loop or SDC Pump shall be operable at all times except all RCPs and SDC Pumps may be de-energized for up to one hour provided:

(1) no operations are permitted that would cause dilution of the RCS boron >{.

[lmaintainedatleastconcentration; and (2) core outlet temperature is U

~

10*F below saturation temperature (Ref. 2.1.1, 3.4.1.3).

4.7 Shutdown Cooling System LTOP relief shall not be isolated from the RCS until RCS cold leg temperatures are greater than 240 F (290 F for Unit 3).

(This is 5 F core restrictive than Ref. 2.1.1,3.4.8.3.1.)

4.8 The RCS chemistry shall be maintained within the following limits:

(Ref. 2.1.1, 3.4.6) e.s J. e Chloride

< 0.15 ppm Fluoride

< 0.15 ppm Olssolved Oxygen 0.10 ppm (with Tave > 250*F) 4.9 The following restrictions shall be observed when starting a Reactor Coolant Pump:

.)

4.9.1

' With the Steam Generators between zero and 10 F above i

the Primary System Temperaturr., then Pressurizer Level shall be less than 60%.

4.9.2 With the Steam Generators between 10 and 20 F above the Primary System Temperature, then Pressurizer level shall be less than 33%. (This is 80 F to 90*F more restrictive than Ref. 2.1.1,3.4.1.3.)

4.10 Starting a RCP is prohibited when the Steam Generators are greater than 20 F above the Primary System Temperature. (Analysis has shown that the resultant pressure rise may challenge the LTOP setpoint regardless of the size of the Pressurizer Bubble) 4.11 Due to core uplift considerations, four RCPs shall not be operated simultaneously until DCS temperature exceeds 500*F.

J 4.12 RCS temperature shall not exceed 350*F, or a pressure of 375 psia when Shutdown Cooling is in service.

4.13 RCS Temperature shall not exceed 340*F until Steam Generator secondary chemistry is within limits.

4.14 At least 2 Reactor Coolant Pumps must be in operation for normal operation of Pressurizer Spray (Reference i. 4.1.2).

(

_r a

4 UNilS 2 AND 3 EEVisiOU1$

Pbb0 bF 94 4.0 PRECAUTIONS

(

(Continued)

^

4.15 With the RCS in a solid condition or LPSI pump can Icad to pressure, transients and lif ting of SD a

pressure relief valve PSV-9349.

type may be avoided by manually operating PIC-0201 prtor TO changing the status of a Charging or LPSI pump and I changed.monf.toring RCS pressure immediately after the pump, closely l

status is 4.16 If venting the VCT, RCOT or Quench Tank becomes difficult, be necessary to drain the Waste Gas Collection IIcader in accordanc it may with 5023-8-14, Section 6.1, Initial System Lineup.

4.17 change are met prior to changing modes. Caution must 4.18 Pressurizer Spray Valves PV-0100A and PV-01008 should be closed prior to RCP start, c,..gpp uw-4.19 Prior to estabitshing a flydrogen blanket on the VCT, the potentially connected systems must be purged with N1trogen and sampled to ensure Oxygen is less than 1%.

Included are the Storage Tank. Gas Strippers, Waste Gas Surge Tank and In service Was 4

4.20 do not exceed 4.5 inches.When withdrawing CEAs to the Lower 1

(

b 5.0 CHECKLIST (S) t I

5.1 None 6.'O PROCEDURE INITIALS / DATE

.6.1 Prepare the Condensate, Feedwater, and Main Steam System for operation as follows:

6.1.1 Determine if the Condensate and Feedwater Systems are available for operation. (Check one)

/

SRO p. Supv.

1 L

,J r-Yes, perform step 6.1.1.1.

'~

b

_ No, mark N/A for step 6.1.1.1.

.1 Initiate prestart recirculation /

cicanup of the Condensate and Feedwater Systems per 5023-9-7.

4 A1 6.1.2.

Initiate Main Steam lead alignment

/

per $023-2-9.

/ /

LO)c / 2//f/rf

/

//

"?

_...___q dkiTS U Eb~3 bks lb[11 P

1 bF 94 6.0 PROCEDURE (Continued)

(

_ INITIAL.S / DATE 6.2 Indicate which Steam Generator (s) the Chemistry Ocpt.

has directed to be drained and ref flied.

(Checkone)

SR0 0_

upv.

....@7

,' rm.

I; L_J

'S.G.

E-088 and E-089, perform step 6.2.1 C

S.G.

E-088 only, perform step 6.2.1 r,

L8 S.G.

E-089 only, perform step 6.2.1 b

Neither Steam Generator, mark N/A for step 6.2.1 sc;sp 6.2.1 Initiate draining and refilling the indicated Steam Generator (s) per 5023-2-185 k

~

/

~6.3 ti eA chment'1 (2) to prepare' systems for-('

procedure:

(Checkone) 6.4 Determine the initial conditions for entering this

[

/ /

SR0 ps. Supv.

rm L2 The RCS is at 350 psia, the Pressurizer has a steam bubble, and two RCP's are running.

Mark N/A for all steps in Sections 6.5 through 6.9, except steps 6.6.6, 6.6.8 and Section 6.8.

b The RCS is not at 350 psia, or the Pressurizer does not have a steam bubble, or two RCP's are not running.

Perform steps in the normal sequence.

l 6.5 Initiate 5023-3-1.4 to fill and vent the RCS.

(Mark N/A if the Pressurizer is solid or a Pressurizer steam bubble has been maintained.)

1. -/

hfl

/

//

If the S/G's are meeting the requirements of Tich. Spec. 3.4.1.4.1, then limit draining to g

not less than 50% WR otherwise limit to 10% WR (Reference 2.4.1.5)

)

7..,..m- -

UNilS 2 AND 3 j

REVISION 11 PAGk52bF94 6.0 PROCEDURE (Continued)

INITIALS / DATE

(

NOTE:

It is desirable to draw the bubble after p

completing three pump sweeps and pr1or o

to ccmpleting the ff11 and vent procedure yF;,.,

in order to:

..?,'d (

[

kifI.

1)

Minimize the time the RCS is in a solid condition.

If transients did occur, the plant would be less sensitive and easier to control with a bubble.

2)

Commence recirculating the Pressurizer to the RCS carly in the startup to equalize chemistry.

ydME 3)

Use time efficiently to prepare for subsequent heatup.

6.6 Indicate the Presurizer status N

(

SRO Ops. Supv.

O Pressurizer is solid at psia; when directed by 5023-3-1.4 to form a steam bubble,. perform steps 6.6.1 through 6.6.8.

U Pressurizer has a steam bubble; mark N/A for steps 6.6.1, 6.6.3, 6.6.4 and 6.6.5 NOTE:

Expected Pressur!zer heatup rate is 50*F/hr which corresponds to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of preheat j

time prior to forming the steam bubble if the RCS 1s at 150 psta, or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if the RCS is at 350 psfa.

CAUTION The Pressurtzer heatup rate shall not

=

exceed 190*F in any one hour. (Thfs is 10*F more restrictive than Ref. 2.1.1, 3.4.8.2).

UNilS 2 AND 3 REVISION 11 PAGEibF94 3.0 PREREQUISITES UNIT 2.-

INITIALS / DATE 3.1 Prior to use of an uncontrolled (pink) copy of this 4

Station Document to perform work, verify that it is current by checking a controlled copy and any TCNs;

/f or by use of the method described in 50123-VI-0.9.. l*l@ / 2//Vss List any appitcable TCNs or wrf te none. t[pf hj

//

. 3.1.1 c;

h/

Ak TS

//

3.2 On-Shift SRO Ops. Supv. approval obtained.

(SR0 Ops. Supv. Inttials) l.X)/T / s,h>IT 3.3 In order to safely and efficiently start up a unit, equipment deff etencies shall be reviewed to identify impact on the startup and corrective action inttfated to minimize the impact. Particular attention must be paid to equipment protective circuits, control schemes r ig.'..,

and Control Room indications. A careful inspection of control board tags and control system status shall be made. Equipment deffetencies affecting the startup sequence shall be Itsted and the Plant Superintendent, or his designee, shall review the Itst indicating which items must be corrected prior to performing the impacted evolution.

For examp1e, if the automatic Gland Steam 3

Pressure Regulating System was unavailable, the 4

(

Superintendent, or his designee, would decide whether the startup should be held pending repair and testing of the Gland Steam System Controls or approve proceeding with the startup using manual control of gland steam pressure. This evaluation of degraded equipment availabtitty should initially be performed in parallel with the vertf tcation or performance of system alignments to support startup and re-evaluated prior to commencing major evolutions such as heatup, vacuum pull, criticality and turbine roll.

/

3.4 The Auxiliary electrical buses are energized.

/

/

LS 3.5 The Plant Protection System is energized and the

[

// '

AS PZR pressure bypass key locks are in I

3.6 If the RWST level is below 80%, then the RAS has been

. suppressed to prevent loss of shutdown cooling while filling the RCS. (N/A if RWST >80%)

/

I 3.7 Ensure the condensate Storage and Transfer System has been aligned per 5023-9-5, Attachment 3(4),

/

Condensate Storage and Transfer System Alignment.

K / L//

[

//

6

w./

NULLLAR GLNLRAI10N SITE UNITS 2 AND 3 OPERATING INSTRUCTION 5023-5-1.3 REVISION 11 PAGE 8 0F 94 3.0 PREREQUISITES (Continued)

(

INITIALS / OATE 3.8 Ensure the Demin. Vater Storage Fact 11ty has been aligned per 5023-11-6, Attachment 1, Demin. Water Storage Fact 11ty Initial Alignment.

fM.J f

7-j 3.9 Level in the Condensate Storage Tanks is above

l. T.S. Limits of 97% for T-121 and above 56% for T-120 ' $

I or malcup operattoris are in progress per 5023-9-5.

Revel requirements must be attained for Mode 3 entry.)

-/

3.10 At least 30,000 gallons of capactty exf sts in the

/

/

radwaste primary tanks to receive radwaste due to unit heatup, oz Radwaste Processing is in progress to provide the required capacity, fj c /1//ff_/_5 3.11 The Charging Pump pulsation dampeners are charged AJ' to the pressures stated in S023-3-2.1, Attachment 7 CVCS Pulsation Dampener Operation.

~/

4.0 PRECAUTIONS 4.1 (UNIT 3ONLY) A RCS heatup of 8'F in any one hour shall not be exceeded when cold leg temperature is J.

< 110'F.

(This is 2*F more restrictive than i

(

Ref. 2.1.1, 3.4.8.1. )

4.2 A RCS heatup rate of 25*F in any one hour shall not be exceeded when cold leg temperature is

< 300*F ( < 330*F for Unit 3).

{This is 5 F more restrictive than Ref.

3 2.1.1,3.4.8.1.)

4.3 A RCS heatup of 50*F fn any one hour shall not be exceeded when cold leg temperature is above 300'F (330*F for Unit 3). (This is 10*F more restrictive than Ref. 2.1.1, 3.4.8.1.)

4.4 The Pressurtzer heatup rate shall not exceed 190*F in any one hour.

(This is 10*F more restrictive than Ref. 2.1.1, 3.4.8.2.)

4.5 In Mode 5 with RCS Loops (filed, at least one RCP or SOC Pump shall be in operation and one of the

,following additional requirements must be met:

,(References 2.1.1,3.4.1.4.1) 4.5.1 One additional RCS Loop or SDC Train is operable of 4.5.2 The water level is t 50% WR in each S.G.

9 9

4 i

.M UNITS 2 AND 3 EEilSib[15 Pb 0 96 4.0 PRECAUTIONS (Continued)

(\\

4 4.6 In Mode 4, a RCP or SDC Pump shall be operating and a second RCP/ Loop or SDC Pump shall be operable at all times except all RCOs and SDC Pumps may be de-energized for up to one hour provided:

(1) no operations are permitted that would cause dilution of the RCS boron

..V

.7

[I maint'af ned at least 10*F below saturation temperature concentration; and (2) core outlet temperature is

'/y (Ref. 2.1.1, 3.4.1.3).

4.7 Shutdown Cooling System LTOP relief shall not be isolated 4

from the RCS untti RCS cold leg temperatures are greater t

than 240*F (290*F for Unit 3).

(This is 5*F more restrictive than Ref. 2.1.1,3.4.8.3.1.)

4.8 The RCS chemistry shall be maintained within the following ifmits:

(Ref. 2.1.1, 3.4.6)

. J.,

ee.

Chloride

< 0.15 ppm Fluoride

< 0.15 ppm Olssolved Oxygen < 0.10 ppm (wfth Tave > 250*F) 4.9 The following restrictions shall be observed when starting a Reactor Coolant Pump:

4.9.1 With the Steam Generators between zero and 10*F above t

the Primary System Temperature, then Pressurtzer Level shall be less than 60%.

4.9.2 WIth the Steam Generators between 10 and 20*F above the Primary System Temperature, then Pressurtzer Level shall be less than 33%. (This is 80*F to 90*F more restrictive than Ref. 2.1.1,3.4.1.3.)

4.10 Starting a RCP is prohibited when the Steam Generators are greater than 20*F above the Primary System Temperature. (Analystshas shown that the resultant pressure rise may challenge the LTOP setpoint regardless of the size of the Pressurizer Bubble) 4.11 Oue to core upitft considerations, four RCPs shall not be operated simultaneously untti RCS temperature exceeds 500*F.

j 4.12 RCS temperature shall not exceed 350*F, or a pressure of 375 psia when Shutdown Cooling is in-service.

4.13 RCS Temperature shall not exceed 340*F untti Steam Generator secondary chemtstry is within limits.

t 4.14 At least 2 Reactor Coolant Pumps must be in operation for normal operation of Pressurtzer Spray (Reference 2.4.1.2).

(

4 UNIIS 2 AND 3 EEibS$0h11 PbEAbF94 4.0 PRECAUTIONS

(

(Continued) 4 4.15 With the RCS in a solid condition or LPSI pump can lead to pressure, transients and lifting of SD pressure relief valve PSV-9349.

changing the status of a Charging or LPSI pu

[I chang'ed.. monitoring RCS pressure immediately after the pump, closely status is 4.16 If venting the VCT, RCOT or Quench Tank becomes difficult, i

be necessary to drain the Waste Gas Collection Header in acco with 5023-8-14, Section 6.1, Initial System Lineup.

i 4.17 Caution must be exercised to ensure all change are met prior to changing modes. prerequisites for a mode 4.18 prior to RCP start. Pressurizer Spray Valves PV-0100A and PV-01 u,.x,a p 4.19 Prior to estabitshing a Hydrogen blanket on the VCT, the potentially connected systems must be purged with Nitrogen and i

sampled to ensure Oxygen is less than IL Gas Strippers, Vaste Gas Surge Tank and In-service Waste Gas Included are the Storage Tank.

4.20 do not exceed 4.5 inches.When withdrawing CEAs to the lo t

i'

\\

5.0 CHECKLIST (S) 5.1 None 6.0 PROCEDURE INITIALS / OATE 6.1 Prepare the Condensate, Feedwater, and Main Steam System for operation as follows:

6.1.1 Octermine if the Condensate and Feedwater Systems are available for operation. (Check one)

/

SRO p. Supv.

I Yes, perform step 6.1.1.1.

No, mark N/A for step 6.1.1.1.

.1 Initiate prestart rectrculation/

cleanup of the Condensate and

.j Feedwater Systems per 5023-9-7.

r/A1 6.1.2 Initiate Main Steam lead alignment

/

per 5023-2-9

/

_ }< / 2//f JT

/

m

-../

1

..p....

i us e.nn e a e.u aetJ s nub 4 &uit Jut.J"3 1.J HNITS 2 ANO 3 REVISION 11 PAGE 11 0F 94 1

i i

6.0 PROCEDURE (Continued) i

(

INITIALS / OATE 6.2 Indicate which Steam Generator (s) the Chemistry Dept.

a has directed to be drained and refilled.

(Check one)

_//1 SRO O upv.

.;..[Q:

IO S.G.

E-088 a'nd E-089, perform step 6.2.1 O

}

S.G.

E-088 only, perform step 6.2.1 1-

[

O S.G.

E-089 only, perform step 6.2.1 i

d k

b 1

Neither Steam Generator, mark N/A for step 6.2.1 ct. gay i

w*-

1 6.2.1 j

Initiate draining and reft 11tng the indicated Steam Generator (s) per j

5023-2-188 Mk

/

6.3 i te A chment 1 (2) to prepare systems for i

i

(

6.4

/'

/ /

Determine the inttf al conditions for entering this

/

j procedure: (Check one) j ps. Supv.

RO 1

l O

The RCS ts at 350 psia, the Pressurtzer j

has a steam bubble, and two RCP's are running.

j Mark N/A for all steps in Sections 6.5 through 6.9, except steps 6.6.6, 6.6.8 and t

Section 6.8.

s N

l The RCS is not at 350 psia, or the Pressurizer does not have a steam bubble, or i

two RCP's are not running. Perform steps in j

the normal sequence.

I I

i' 6.5 Initiate 5023-3-1.4 to (111 and vent the RCS.

1 l

(Mark N/A if the Pressurizer is solfd or a Pressurizer steam bubble has been maintained.)

k#-./@,/Y/

l i

/

/ /

5 If tiie S/G's are meeting the requirements of Tech. Spec. 3.4.1.4.1, then Ilmit draining to 4

not less than 50% WR otherwise limtt to 10% WR 1

(Reference 2.4.1.5)

I a-i i

. _, _ ~ _, -..... - _ _. _. _ _ _..,, _ _. _. _ _, _.,, _

,. _., _ _ _. _., _ _. _,. _ _ _ _. - _ _,. _., _. _.. ~. _ _ _. _..

..m 4

UN115 2 AND 3 REVISION 11 PAGEi[bF94 6.0 PROCEDURE (Continued)

(

INITIALS / DATE NOTE:

It is desirable to draw the bubble after completing three pump sweeps and prior to ccmpletIng the ff11 and vent procedure.-fif;,.

in order to:

..7,7. ?,

. 3.<&

st

.e 1)

Mfnfmize the time the RCS is in a solid condition.

If transients did occur, the plant would be less sensitive and easter to control with a bubble.

2)

Commence recirculating the Pressurtzer to the RCS early in the sta. tup to equalize chemtstry.

yM.....F 3)

Use time efficiently to prepare for subsequent heatup.

6.6 Indicate the Presurizer status (Checkone):

'l 7

g

$RO Ops. Supv.

Pressurtzer is solid at psta; when directed by 5023-3-1.4 to fann a steam bubble,. perform steps 6.6.1 through 6.6.8.

O Pressurtzer has a steam bubble; mark N/A for steps 6.6.1, 6.6.3, 6.6.4 and 6.6.5 NOTE:

Expected Pressur1zer heatup rate is 50*F/hr which corresponds to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of preheat 3

time prior to forming the steam bubble f f the RCS is at 150 psf a, or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if the RCS is at 350 psfa.

CAUTION The Pressurtzer heatup rate shall not exceed 190*F in any one hour. (This is 10*F more restrictive than Ref. 2.1.1, 3.4.8.2).

l m

p - t '? - M SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 1 0F 9 ATTACHMENT 8.1 CHECK-OFF LIST 1 TCN 7 - 8 HIGH PRESSURE SAF'ETY INJECTION SYSTEM FLOWPATH VALVE ALIGNMENT - UNIT 2

~

DATE O.

ig55-TIME \\%'b O 1.0 PRERdQUISIT5S INITIALS 1.1 Prior to use of an uncontrolled (pink) copy of this Station Occument to perform work, verify that it is current by checking a controlled copy an any TCNs or by use of the method described in 50123-VI-1.0.

tt 1.1.1 List all applicable TCNs or write N.A.

w_

% --~ %

WNY 1.2 On-shift SRO-Operations Supervisor appreval obtained.

(SRO OPS SUPV Initials) 4 NOTE:

ALL LOCKED VALVES ARE LOCKE0 WITH AN ESF LOCK.

NOTE:

(1) Verify by CR-57 indication.

rw (2) Safety Injection Tank outlet valves are required i

to be open in Modes 1-3 when RCS pressure is greater than 40 psia.

CAUTION If a valve in this Check-Off List requires fI repositioning, then contact the C.O. for approval prior to repositioning.

2.0 PROCEDURE REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.1 Berated Water Supply 2.1.1 2HV-9305 Containment Emergency Sump Outlet Valve OPEN M

')2.1.2 2HV-9304 Containment Emergency Sump Outlet Valve OPEN M/

y 2.1.3 2HV-9302 Containment Emergency Sump Outlet Valve (in Tendon Gallery)

CLOSED b

l w

/

1. 2.1.4 2HV-9303 Containment Emergency

/

3 3

Sump Outlet Valve (in Tendon Gallery)

CLOSE b

I 2.1.5 521219MUO68 Safety Injection Pump l

Rectrc. to RWST T-005 LOCKE0 (Aux. Fd. Bldg. Roof)

OPEN o r holdnhQQ

{,,

o vw'm s s

N e

~

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTICN S023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 2 0F 9 ATTACHMENT 8.1 CHECK.QFF LIST 1 s.

TCN

('b 2.0 PROCEDURE (Continued')

REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.1.6 2HV-9300 RWST 2T-005 Outlet Valve LOCKED (2T-005 Tank Room)

OPEN k

(KEY REMOVED)

CR-57 2.1.7 2HCV-7767 RWST 2T-005 X-C'onn. to LOCKED

/

RWST 2T-006 OPEN

~

/

(2T-005 Tank Room)

[ /J, 2.1.8 2HCV-7766 Cross-connect 2T-006 to LOCKED 2T-005 (2T-006 Tank OPEN V V Room)

[

2.1.9 2HV-9301 RWST 2T-006 Outlet LOCKED

'k M.

Valve (2T-006 Tank Room) OPEN

~

(KEY REMOVED)

CR-57 5

M 2.1.10 S21219MUO67 Gravity Feed to LOCKED T

Charging Pumps OPEN

/

f (2T-006 Tank Room) 2.1.11 521219MUO70 Spent Fuel Pool Make-up Pump Suction CLOSED (2T-006 Tank Room) 2.2 Hiah Pressure Safety Injection Pump 2P-017 (SEB Rm. 005) 2.2.1 521204MU184 Miniflow Orifice LOCKED 2F0-9314 Bypass Valve CLOSED

/

2.2.2 521204MUO34 HPSI Pump 2P-017 LOCKED jp Minimum Recirc. Valve OPEN fG i-2.2.3 521204MU007 HPSI Pump 2P-017 LOCKED Suction Valve OPEN

/

2.2.4 521204MU190 Suction Relief LOCKED Isolation Valve OPEN

/M 2.2.5 521204MUU12 HPSI Pump 2P-017 LOCKED

/

Discharge Valve OPEN 2.3 High Pressure Safety Injection Pump 2P-018 (Third of a Kind)

(SEB Rm. 015) 2.3.1 521204MU013 HPSI Pump 2P-018 Discharge to HPS! #1 Header (Rm. 005);

LOCKED Jg l

mark NA if not.

OPEN f

l

.. w s

SAN ONOFRE NUCLEAR GENERATING 5 % TION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 3 0F 9 ATTACHMENT 8.1

{

CHECK-0FF LIST 1 TCN q 2.0 PROCEDURE (Continued)

REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.3.1.1 When 2P-018 is aligned to "B" train or LOCKED is removed from service; mark NA if not. CLOSED MA /

2.3.2 521204MU010 HPSI Pump 2P-018 Train A Suction Valve (RWST 2T-005)

(Passage between SEB LOCKED Rms. 005 and 015);

OPEN f_/

mark NA if not.

.1 When 2P-018 is aligned to "B" train or LOCKED is removed from service; mark NA if not. CLOSED NA /

K3.3 S21204MU191 Suction Line Relief LOCKED Valve Isolation OPEN h

2.3.4 S21204MU011 HPSI Pump 2P-018 Train B Suction Valve (RWST LOCKED 2T-006); mark NA if not. CLOSED

/

v.

m

.1 When 2P-018 is aligned to "B" train; LOCKED mark NA if not.

OPEN NA/

2.3.5 521204MU186 Bypass around mini-flow LOCKED orifice 2F0-9313 CLOSED J

2.3.6 521204MUO36 HPSI Pump 2P-018 Train A Minimum Recirc. Valve; LOCKED mark NA if not.

OPEN

.1 When 2P-018 is aligned for service on LOCKED Train 8 or is removed from service; CLOSED NA /

mark NA if not.

2.3.7 S21204MU104 HPSI Pump 2P-018 Train B Minimum Recirc. Valve; LOCKED mark NA if not.

CLOSED

/

.1 When 2P-018 is aligned for service LOCKED on Train B; mark NA if not.

OPEN

/

2.3.8 S21204MUOl6 HPSI Pump 2P-018 LOCKED Discharge Valve OPEN 2.3.9 S21204MU014 HPSI Pump 2P-018 Discharge to HPSI #2 Header; LOCKED mark NA if not.

CLOSED

.1 When 2P-018 is aligned to "B" train; LOCKED mark NA if not.

OPEN h/

~m

)

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 4 0F 9

~'

ATTACHMENT 8.1

(

CHECK-OFF LIST 1 TCN 7-8 2.0 PROCEDURE (ContinucJ)

REQUIRED INITIALS STEP COMPONENT DESCRIPTION f STATUS IST/2ND g

2.4 Htqh Pressure Safety Injection Pump 2P-019 (Rm. 002) 2.4.1 521204M0189 Suction Line Relief LOCKED Valve Isolation OPEN

//g 2.4.2 521204MU009 HPSI Pump 2P-019 LOCKED Suction Valve OPEN

/

2.4.3 521204MU185 Bypass around Mini-flow LOCKED j

orifice 2FO-9315 CLOSED 2.4.4 521204MUO35 HPSI Pump 2P-019 LOCKED Minimum Rectrc. Valve OPEN F

i 2.4.5 521204MUO15 HPSI Pump 2P-019 LOCKED Discharge Valve OPEN

/,

s.

2.5 High Pressure Safety Injection Header #1 O*$

2.5.1 2HV-9330 HPSI #1 Header to Loop 2A (ren. 39)

CLOSED jgfM 2.5.2 2HV-9420 HPSI #1 Header to Hot

//j/W "M J

Leg Injection (Pen 71)

CLOSED F-2.5.3 521204MU154 Charging Pump to Hot leg Injection Block Valve (near Pen 71)

CLOSED //jN 2.5.4 2HV-9327 HPSI #1 Header to Loop 1B (Pen 5)

CLOSED gdfjd/

2.5.5 2HV-9324 HPSI #1 Header to Loop 1A (Pen 3)

CLOSED pdik/

2.5.6 2HV-9333 HPSI #1 Header to Loop 2B (Pen 41)

CLOSED g/$/M/

/

2.6 H'ich Pressure Safety Injtetton Header #2 2.6.1 2HV-9329 HPSI Header #2 to Loop 2A (Pen 39)

CLOSED gd

/ _

7 9 2.6.2 2HV-9326 HPSI Header #2 to Loop IB (Pen 5)

CLOSED //d/k/#

u 2.6.3

'2HV-9323 HPSI Header #2 to h/k [

Loop 1A (Pen 3)

CLOSED L

W J

SAkONOFRENUCLEARGENERATINGSTATION OPERATING INSTRUCTION $023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 5 0F 9 ATTACHMENT 8.1 CHECK-0TF LIST 1 TC N 7_ - 8.

2.0 PROCEDURE (Continued)

REQUIREO INITIALS S_T Q COMPONENT DESCRIP. TION STATUS IST/2ND k.6.4 S2120SMU005 Charging Pump to Hot leg Injection Block fE Valve (near Pen 71)

CLOSED g f _-/

2.6.5 2HV-9434 HPSI Header #2 to Hot

/)

Leg injection (Pen 67)

CLOSED

//$M L- - k 2.6.6 2HV-9332 HPSI Header #2 to Loop 20 (Pen 41)

CLOSED g/(Mk/i_

2.7 HPSI-Hot leg Injection to Loop #1 (inside Containment) 2.7.1 2HV-9437 Hot leg Injection Drain Valve to RCS Drain Tank

/

/dk [,f_

(17' by Pen 67)

CLOSED

.1 2HV-9437 Actuator Air

((M(7

{

Supply Valve OPEN O

2.7.2 521204M0066 Hot leg Injection

rc Block Valve to Loop #1 LOCKED M

/

//d k

/

(17' by Pen 67)

OPEN l

2.8 HPSI-Hot leg Injection to loop #2 (inside Containment) 2.8.1 2HV-9433 Hot leg Injection to Loop #2 Orain to RCS Drain Tank (by Cntmt.

g Emer. Sump)

CLOSED g?) k M L

.1 2HV-9433 Actuator Air Supply Air Supply Valve OPEN

///idIlT[

2.8.2 521204MUO67 Hot Leg Injection to Loop #2 Block Valve (17' in overhead by LOCKED

/

[fff ko Cntmt. Emer. Sump)

OPEN f

2.9 Safety Injection Tanks 2.9.1 Safety injection Tank 2T-010

.1 2HV-9370 SIT 2T-010 Outlet to (2) OIWi s, /

Reactor Coolant Loop 20 Q o j/ ) g/)b

__/

t/dh/_M

.2 2HV-9372

$1T Fill Valve CLOSED NOTE:

(2) Safety Injection Tank cutlet valves are required to be open in Moden 1-3 when RCS pressure is greater than 400 psia.

"W

~

i SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 6 0F 9 ATTACHMENT 8.1 CHECK-0FF LIST 1 TCN _7 g 2.0 PROCEDURE (Continued)

~~

REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.9.1.$ S22417MR063 2HV-9372 Air Supply OPEN

///jM

.4 2HV-9371 SIT Check Valve Leakage CLOSED f/d/ L Drn. Valve ffd

.5 522417MR062 2HV-9371 Air Supply OPEN 2.9.2 Safety Injection Tank 2T-009

.1 2HV-9360 SIT 2T-009 Outlet to (2 g /l k.

Reactor Coolant Loop 2A OSE

/

.2 2HV-9361 SIT Check Valve Leakage CLOSED ///Nt/

Drn Valve

.3 522417MR064 2HV-9361 Air Supply OPEN

/dI/h[t/M jf/J_/jI&f y

4 2HV-9362 Sli Ft11 Valve CLOSED

.5 522417MR065 2HV-9362 Air Supply UPEN gy$

2.9.3 Safety Injection Tank 2T-007

.1 2HV-9350 Sli 2T-007 Outlet to (2) OED Reactor Coolant loop 18 LOS f f///_ M _ __

g//1 N W

.2 2HV-9352 Sli Ft11 Valve CLOSED

.3 522417MR071 2HV-9352 A1r Supply OPEN fgdM___.

.4 2HV-9351 Sli Check Valve Leakage CLOSED ged/M Orn Valve jff)fk

.5 522417HRG70 2HV-9351 Air Supply OPEN 2.9.4 Safety Injection Tank 27-008

.1 2HP9340 SIT 2T-008 Outlet to (2) OPEN/_

ReactorCoolantLoop1ACCJLO51.Il g4/k/

C 5 f

.2 2HV-9342 S!T Fill Valve CLOSED

[8j_(k 3 522417HR069 2HV-9342 Air Supply OPEN M/_

NOTE:

(2)SafetyInjectionTankoutletvalvesare required to be open in Modes 1-3 when RCS pressure is greater than 400 psta.

Q U

s' SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 7 0F 9 ATTACHMENT 8.1 fC

\\

~

2.0 PROCEDURE (Continued)

REQUIRED INITIALS STEP COMPONENT DESCRIPTION NOTE STATUS IST/2ND

[2.9.4.4 2HV-9341 SIT Check Valve Leakage CLOSE0 [ [

Orain Valve

.5 522417MR068 2HV-9341 Air Supply OPEN g[l[QE/

2.9.5 Safety Injection Tank 2T-008 (63')

.1 2HV-9344 SIT 2T-008 Nitrogen

/

Supply Valve (1)

CLOSE08/J/p

\\

2.9.6 Safety Injection Tank 2T-007 (63')

.1 2HV-9354 SIT 2T-007 c

Nitrogen Supply (1)

CLOSE M / k /

Valve 2.9.7 Safety Injection Tank 2T-009 (63')

.1 2HV-9364 SIT 2T-009 Nitrogen Supply Valve (1)

CLOSE0//jalYf l2 -

2.9.8 Safety Injection Tank 2T-010 (63')

.1 2HV-9.374 511 2T-010 Nitrogen Supply Valve (1)

CLOSE0gdlf/f 2.9.9 Safety Injection Tank Orain Header (inside Containment) (30')

.1

$21204MUO68 Sli Orain to RWST LOLKED (Pen. 6)

OPEN

/../

.2 2HV-9335 SIT Drain to RCS Drain Tank (next to Diological Shield Access)

CLOSED

.3 2HV-9334 Sli Orain Header to RWST (inside Pen 6)

CLOSED 2.9.10 Main Control Board Indication

.1 2HV-9345 2T-008 Vent Valve CLOSEDM

.2 2HV-9355 2T-007 Vent Valve CLOSE

/

' NOTE:

(1) Verify by CR-57 indication.

e

W s

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION ~S023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 8 0F 9 ATTACHMENT 8.1

(

CHECK-OFF LIST 1 TCN,7-g 2.0 PROCE00RE (Continued)

REQUIRED INITIALS STEP COMPONENT DESCRIPTIONe STATUS IST/2ND 2.9.10.3 2HV-9365 2T-009 Vent Valve CLOSED

/ $_,__

gfg((_

.4 2HV-9375 2T-010 Vent Valve CLOSED 2.10 Safety injection Pump Minimum Recirc.

2.10.1 2HV-9347 Safety injection 2P-018 Minimum Recirc. to RWST OPEN

/_

2.10.2 2HV-9348 Safety Injection 2P-018

/

Minimum Recirc. to RWST OPEN g

/

2.10.3 2HV-9306 Safety Injection 2P-018 Minimum Recirc. to RWST OPEN

/

2.10.4 2HV-9307 Safety Injection 2P-018 8

Minimum Recirc. to RWST OPEN

/

f' y

2.11 Safety Injection Tank Orain Header Y

2.11.1 521204MUO99 SIT Orain to RWST LOCKED (at Pen 6)

CLOSED 2.11.2 S21204MUO49 SIT Orain to RWST LOCKED (SW Pen Area)

OPEN g/

r 2.11.3 521219MUO38 Spent Fuel Pool Ion Exch to RWST Block f/

Valve (30' Pen near

/

4 h

f f/8 Pen 67)

CLOSED 2.11.4 S21204MUO60 SIT Orain Line to LOCKED

[

RWST Isolation Valve CLOSED

't a

h a

m

W J

1

~

~

SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 OPERATING INSTRUCTION S023-3-2.7 REVISION 7 PAGE 9 0F 9

^

(

ATTACHMENT 8.1 CHECK-OFF LIST 1 TCN 7-8 PERFORMED BY:

//M DATE/ TIME 3 S N f../f f'1 Ope nitia s

~

PERFORMED BY:

_/

DATE/ TIME # YN M/

g' tJF In"rth VERIFIED BY:

w

/

b45:._

DATE/ TIME._ Z -/f'3I / /85f' Opera + r Initials VERIFIED BY:

DATE/ TIME F/PhY/fdv Operator Initials

~

/

NOTE:

SRO Ops. Supv. shall not sign " Reviewed By" until all comments in relation to this Check-Off List have been resolved 1.e.: TCNs written and incorporated, caps and flanges installed, locks and chains in place, etc.

REVIEWED BY:

DATE/ TIME 2-/O'<Y6- /FYO 5 0 Ops. Supv.

..t FILE DISPOSITION: Fi per 5023-0-28 7

COMMENTS: @

q ' &! is u, !v e l a ju a ll:va

' - d w =: a I

4 6

e 0139g

& m N

.....tm %:ht u T20N $1TE Us115 2 ANO 3

~

REVl510N 2 OPERATING th ATTACHMENT 2 Pact 20 or 28 PRO

~ CEDURE SIGNATURE SUPPLEMENT

~

Sheet _

_ of _

AFFECTED PROCEDURE:

CHECKLIST NUMBER *50 Oc2 3-3 d )

2 t

_ REv!SION 2

TCH REVISION

_ TCN

'// //

f

. j y I (-ff PERFORMED BY:

8 PERFDRMED BY:

PERFORMED B 07IRTDUIRIT tiXTT7 T 0

PERFDRMED BY:

A PERFORMED BY: hE y f:!

CPERATOR/INIT DATE OPI R/INI

'5#

RFORMED BY:

PERFORMED BY:

OPERATOR /INIT DATE OTEEAioR/INITTATI77IRt PERFORMED BY:

~

PERFORMED BY:

0FiETUR71RIT V 1E/T1 0

A PERFORMED BY:

VERIFIED BY:

0FTETDT/IRITT4TC/ TIR OP n /Ju GR/lRITTATUTIRE VERIFIED BY:(

M@

VERIFIED BY:

MG At'd y

M/lNIT DATE7

~M 9

M 10RIINJT DATE/ily ( VERIFIED BY:

~

VERIFIED BY:

8f N7/4Tih UT/IRITTATUTIRE 0i TE7 TIRE VERIFIED BY:

VERIFIED BY:

0FEAITDT/IRIT DITUTTT I 'I #N OR/'IN A

IIiQ VERIFIED BY:

VERIFIED BY:

6F[EITDI7IRITDATE7 TIRE MT R/INITTATUTIRE YERIFIED BY:

INDEP. VER. B cFEXIT5K71RITTXTUTIRT I

(D INDEP. VES. BY:

INDEP. VER BY:

. 2*K//lo OAIE/ TIME INDEP. VER. BY:

INDEP. VER. BY:

dFERT5X71RITTXTUTIRC A

I INDEP. VER BY:

M INDEP. VER. SY:

@lRATOR/INIT DATE/TIM A

//t 73 DFE y,

INDEP. VER BY:

INDEP. VER BY:

OTERTUR71RITWUTIET 22k7 DNTDR/1 NIT-@lNDEP. VER. BY:

9 dFERAT5if/INIT~DATE/TIEC ATTACHMENT 2 PAGE 1 0F )

^

2 ?

,9 SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE I 0F 9 ATTACHMENT 8.1 CHECK-OFF LIST 1 TCN 7-8

~

HIGH PRESSURE SAFETY INJECTION SYSTEM FLOWPATH VALVE ALIGNMENT - UNIT 2 DATE QL.

is tg TIME \\Wh O 1.0.PRERf0 VISITS INITIALS 1.1 Prior to use of an uncontrolled (pink) copy of this Station Document to perform work, verify that it is current by checking a controlled copy an any TCNs or by use of the method described in 50123-VI-1.0.

cL 1.1.1 List all applicable TCNs or write N. A.

c_

NY 1.2 On-shif t SRO-Operations Supervisor approval obtained.

(SRO OPS SUPV Initials)

NOTE:

ALL LOCKED VALVES ARE LOCKED WITH AN ESF LOCK.

NOTE:

(1) Verify by CR-57 indication.

n (2) Safety Injection Tank outlet valves are required i

to be open in Modes 1-3 when RCS pressure is greater than 40 psia.

/

CAUTION If a valve in this Check-Off List requires f

repositioning, then contact the C.O. for

===----

approval prior to repositioning.

2.0 PROCEDURE REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.1 Borated Water Supply r

2.1.1 2HV-9305 Containment Emergency Sump Outlet Valve OPEN M

3 tr 2.1.2 2HV-9304 Containment Emergency i

Sump Outlet Valve OPEN M/

'l

'y 2.1.3 2HV-9302 Containment Emergency Sump Outlet Valve (in Tendon Ga11ery)

CLOSED b

]

/

g?". 2.1.4 2HV-9303 Containment Emergency

/

T Sump Outlet Valve t

(in Tendon Gallery)

CLOSE bb i

f I

2.1.5 521219MUO68 Safety Injection Pump l

Recirc. to RWST T-005 LOCKED (Aux. Fd. 81dg. Roof)

OPEN t

i

um

...g SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION-5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 2 0F 9 ATTACHMENT 8.1 CHECK,QFF LIST 1 TCN

(~b 2.0 PROCEDURE (Continued')

REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND

'2.1.6 2HV-9300 RWST 2T-005 Outlet Valve LOCKED (2T-005 Tank Room)

OPEN

/ k~

(KEY REMOVED)

CR-57 2.1.7 2HCV-7767 RWST 2T-005 X-C'onn. to LOCKED RWST 2T-006 OPEN

/

(2T-005 Tank Room)

[ g, 2.1.8 2HCV-7766 Cross-connect 2T-006 to LOCKED 2T-005 (2T-006 Tank OPEN v V Room) t 2.1.9 2HV-9301 RWST 2T-006 Outlet LOCKE0

- k M.

Valve (2T-006 Tank Roca) OPEN (KEY REMOVED)

~

CR-57

/?

Ph 2.1.10 521219MUO67 Gravity Feed to LOCKED T

4, Charging Pumps OPEN

/

s (2T-006 Tank Room) e 2.1.11 521219MUO70 Spent Fuel Pool Make-up Pump Suction CLOSED (2T-006 Tank Room) 2.2 Hioh Pressure Safety Injection Pump 2P-017 (SEB Rm. 005) 2.2.1 521204MU184 Miniflow Orifice LOCKED

{

2F0-9314 Bypass Valve CLOSED

/

i 2.2.2 521204MUO34 HPSI Pump 2P-017 LOCKED 4

Mir.imum Recire. Valve OPEN fG 1

2.2.3 521204MU007 HPSI Pump 2P-017 LOCKED Suction Valve OPEN 2.2.4 521204MU190 Suction Relief LOCKED Isolation Valve OPEN

/

2.2.5 521204MUO12 HPSI Pump 2P-017 LOCKED Discharge V,alve OPEN 2.3 High Pressure Safety Injection Pump 2P-018 (Third of a Kind)

(SEB Rm. 015) 2.3.1 521204MUO13 HPSI Pump 2P-018 l

Discharge to HPSI #1 Header (Rm. 005);

LOCKED

/ -

mark NA if not.

OPEN f

7

.5 SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 i

UNITS 2 AND 3 REVISION 7 PAGE 3 0F 9 ATTACHMENT 8.1

(

CHECK-OFF LIST 1 TCN po 2.0 PROCEDURE (Continued)

REQUIRED INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.3.1.1 When 2P-018 is aligned to "B" train or LOCKED is removed from service; mark NA if not. CLOSED MA /

2.3.2 S21204MUO10 HPSI Pump 2P-018 Train A Suction Valve (RWST 2T-005)

(Passage between SEB LOCKED I

Rms. 005 and 015);

OPEN

/

mark NA if not.

.1 When 2P-018 is aligned to "B" train or LOCKED is removed from service; mark NA if not. CLOSED N A= /

O2'3.3 521204MU191 Suction Line Relief LOCKED Valve Isolation OPEN h

2.3.4 521204MUO11 HPSI Pump 2P-018 Train B Suction Valve (RWST LOCKED p.

2T-006); mark NA if not. CLOSED

• /

v.

m

.. a

.1 When 2P-018 is aligned to "B" train; LOCKED mark NA if not.

OPEN NA/

r-2.3.5 S21204Mul86 Bypass around mini-flow LOCKED 4

orifice 2FO-9313 CLOSED JP 2.3.6 521204MUO36 HPSI Pump 2P-018 Train A Minimum Recirt. Valve; LOCKED mark NA if not.

OPEN

.1 When 2P-018 is aligned for service on LOCKED Train B or is removed from service; CLOSED NA /

mark NA If not.

2.3.7 521204MU104 HPSI Pump 2P-018 Train 8 Minimum Reci.c. Valve; LOCKED mark NA if not.

CLOSED

/

.1 When 2P-018 is aligned for service LOCKED on Train 3; mark NA if not.

OPEN k/

2.3.8 521204MUJ)6 HPSI Pump 2P-018 LOCKED Otscharge Valve OPEN 2.3.9 S21204MUO14 HPSI Pump 2P-018 Otscharge to HPS! #2 Header; LOCKED mark NA if not.

CLOSED

/

.1 When 2P-018 is aligned to "B" train; LOCKED mark NA if not.

OPEN k/

s f

3 SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 4 0F 9 ATTACHMENT 8.1

(

CHECK-0F LIST 1 TCN 7 2.0 PROCEDURE (Continued)

REQUIRED INITIALS STEP COMPONENT DESCRIPTION.

STATUS IST/2ND I

l 2.4 High Pressure Safety Infection Pump 2P-019 (Rm. 002) 2.4.1 521204MU189 Suction Line Relief LOCKED Valve Isolation' OPEN

//g 2.4.2 521204MU009 HPSI Pump 2P-019 LOCKED Suction Valve OPEN

/

j 2.4.3 521204MU185 Bypass around Mini-flow LOCKED orifice 2FO-9315 CLOSED 2.4.4 521204MUO35 HPSI Pump 2P-019 LOCKED b

Minimum Rectre. Valve OPEN F

2.4.5 521204MUO15 HPSI Pump 2P-019 LOCKE0 Discharge Valve OPEN

/

2.5 High Pressure Safety infection Header #1 C'.

2.5.1 2HV-9330 HPSI #1 Header to Loop 2A (Pen. 39)

CLOSED pf/b 2.5.2 2HV-9420 HPSI #1 Header to Hot

/f I

j Leg Injection (Pen 71)

CLOSED

/A M A/ W-2.5.3 521204MU154 Charging Pump to Hot i

Leg Injection Block

)

Valve (near Pen 71)

CLOSED /dh l

2.5.4 2HV-9327 HPSI #1 Header to l

Loop 18 (Pen 5)

CLOSED

// /d/&/

2.5.5 2HV-9324 HPSI #1 Header to V

g/6/k/ @

I Loop 1A (Pen 3)

CLOSED 2.5.6 2HV-9333 HPSI #1 Header to Loop 28 (Pen 41)

CLOSED gj(t/

/

2.6 H'ich Pressure Safety Injection Header #2 2.6.1 2HV-9329 HPSI Header #2 to g

Loop 2A (Pen 39)

CLOSED //df/P/ rt 2.6.2 2HV-9326 HPS! Header #2 to 9

gd/k/ (f'l Loop 10 (Pen 5)

CLOSED l

2.6.3

'2HV-9323 HPS! Header #2 to

//d/k/ [

Loop 1A (Pen 3)

CLOSED

+

p a

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION $023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 5 0F 9 ATTACHMENT 8.1 CHECK-OFF LIST 1 TCN 7-8 2.0 PROCEDURE (Continued)

REQUIRE 0 INITIALS STEP COMPONENT DESCRip, TION STATUS IST/2ND

?

h6.4 ' S'2120BMU005 Charging Pump to Hot leg Injection Block g

g//h y#

Valve (near Pen 71)

CLOSED 2.6.5 2HV-9434 HPSI Header #2 to Hot leg Injection (Pen 67)

CLOSED

/d$/

k 2.6.6 2HV-9332 HPSI Header #2 to Loop 28 (Pen 41)

CLOSED g//fp 2.7 HPSI-Hot Leo injection to Loop #1 (inside Containment) i 2.7.1 2HV-9437 Hot Leg Injection Orain Valve to RCS Orain Tank (17' by Pen 67)

CLOSED / / JI,

.1 2HV-9437 Actuator Air G

Supply Valve OPEN

/d40lI[

f 2.7.2 521204MUO66 Hot leg Injection m

e-Block Valve to Loop #1 LOCKED (17' by Pen 67)

OPEN 8d/

7 2.8 HPSI-Hot leg Injection to Loop #2 (inside Containment) 2.8.1 2HV-9433 Hot Leg injection to Loop #2 Orain to RCS Orain Tank (by Cntmt.

Emer. Sump)

CLOSED g6_k

[_

.1 2HV-9433 Actuator Air Supply Air Supply Valve OPEN

/[/$1 2.8.2 521204MUO67 Hot leg Injection to Loop #2 Block Valve (17' in overhead by LOCKE0 Cntmt. Emer. Sump)

OPEN d/.I he

/

2.9 Safety Injection Tanks 2.9.1 Safety injection Tank 2T-010 l

.1 2HV-9370

$1T27-010Outletto(2)OP W.

j Reactor Coolant loop 28 OSE gf///fV i

.2 2HV-9372 51T Fill Valve CLOSED gM

NOTE:

(2) Safety Injection Tank outlet valves are required to be open in Modes 1-3 when RCS pressure is greater than 400 psia.

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 6 0F 9 ATTACHMENT 8.1 CHECK-OFF LIST 1 TCN_723 2.0 PROCEDURE (Continued)

REQUIREO INITIALS STEP COMPONENT DESCRIPTION STATUS IST/2ND 2.9.1.3 S22417MR063 2HV-9372 Air Supply OPEN

//dh 4 2HV-9371 SIT Check Valve Leakage CLOSED ffd]L Drn. Valve

///h

.5 S22417MR062 2HV-9371 Air Supply OPEN

)

2.9.2 Safety injection Tank 2T-009

.1 2HV-9360 SIT 2T-009 Outlet to (2

/// 8ll/

Reactor Coolant Loop 2A OSE

/

.2 2HV-9361 SIT Check Valve Leakage CLOSED

///Idlt/

Orn Valve

.3

$22417MR064 2HV-9361 Air Supply OPEN

/d/@//

jf/.f/N/*

fp

.4 2HV-9362 SIT Ft11 Valve CLOSED

.5 S22417MR065 2HV-9362 Air Supply OPEN gggydk 2.9.3 Safety injection Tank 2T-007

.1 2HV-9350 SIT 2T-007 Outlet to (2) 0~LOS ff// W Reactor Coolant Loop 10

/

g/ f/OR/W

.2 2HV-9352

$1T Fill Valve CLOSED

/

g@!

.3 $22417MR071 2HV-9352 Air Supply OPEN 4 2HV-9351 SIT Check Valve Leakage CLOSED gzd/

M Drn Valve

//d/N/

.5 522417MR070 2HV-9351 Air Supply OPEN 2.9.4 Safety injection Tank 2T-003 l

.1 2HV-9340 SIT 2T-008 Outlet to (2) OPEN/_

u Reactor Coolant Loop 1ACC10SJ#

//$/W/ 4 C S

.2 2HV-9342 SIT Fill Valve CLOSED

[l/I/N M/hN/W

.3 522417MR069 2HV-9342 Air Supply OPEN NOTE: (2) Safety injection Tank outlet valves are required to be open in Modes 1-3 when RCS pressure is greater than 400 psta.

m m

....g a

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 7 0F 9 ATTACHMENT 8.1

\\

CHECK-OFF LIST 1 TCN7-8 2.0 PROCEDURE (Continued)

REQUIRE 0 INITIALS STEP COMP 0NENT DESCRIPTION NOTE STATUS IST/2ND

[2.9.4.4 2HV-9341 SIT Check Valve Leakage CLOSED [ Y b Orain valve

.5 522417MR068 2HV-9341 Air Supply OpEN s7 M 2.9.5 Safety Injection Tank 27-008 (63')

.1 2HV-9344 SIT 2T-008 Nitrogen

/

Supply Valve (1)

CLOSED //d/W

\\

2.9.6 Safety injection Tank 2T-007 (63')

.1 2HV-9354 SIT 2T-007 Nitrogen Supply (1)

CLOSE M /4fU Valve 2.9.7 Safety injection Tank 2T-009 (63')

4

.1 2HV-9364 SIT 2T-009 Nitrogen Supply Valve (1)

CLOSE0 h ofU 2.9.8 Safety Injection Tank 2T-010 (63')

.1 2HV-9374 SIT 2T-010 Nitrogen

. Supply Valve (1)

CLOSE0 M alt /

2.9.9 Safety injection Tank Orain Header (inside Containment) (30')

.1 521204MUO68 SIT Orain to RWST LOCKE0tS T h 2 8

27M, (Pen. 6)

OPEN

.2 2HV-9335 S!T Drain to RCS Drain Tank (next to Biological Shield J'

i, Access)

CLOSED MU.M,D -

.3 2HV-9334 SIT Orain Header to RWST (inside Pen 6)

CLOSED ]

2.9.10 Main Control Board Indication

.1 2HV-9345 2T-008 Vent Valve CLOSED ///hMt/

.2 2HV-9355 2T-007 Vent Valve CLOSE

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' NOTE: (1) Verify by CR-57 indication.

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SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.7 UNITS 2 AND 3 REVISION 7 PAGE 8 0F 9

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ATTACHMENT 8.1 CHECK-0FF LIST 1 TCN 7-R 2.0 PROCE00RE(Continued)

REQUIRE 0 INITIALS STEP COMPONENT DESCRIPTION,

STATUS IST/2ND 2.9.10.3 2HV-9365 2T-009 Vent Valve CLOSED

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.4 2HV-937S 2T-010 Vent Valve CLOSED gp/ hit / N 2.10 Safety Injection Pump Minimum Rectre.

2.10.1 2HV-9347 Safety Injection 2P-018

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Minimum Recire. to RWST OPEN

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2.10.2 2HV-9348 Safety Injection 2P-018

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f Minimum Rectre to RWST OPEN jf'

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2.10.3 2HV-9306 Safety Injection 2P-018

• • inimum Recirc. to RWST OPEN

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2.10.4 2HV-9307 Safety Injection 2P-018 Minimum Recirc. to RWST OPEN

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g 2.11 Safety Injection Tank Drain Header Y

2.11.1 521204MUO99 SIT Drain to RWST LOCKED (at Pen 6)

CLOSED 2.11.2 521204MUO49 SIT Drain to RWST LOCKED (SW Pen Area)

OPEN

((

r 2.11.3 521219MUO38 Spent Fuel Pool Ion Exch, to RWST Block Valve (30' Pen near g

Pen 67)

CLOSED fF 2.11.4 521204MUO60 SIT Drain Line to LOCKED g,

RWST Isolation Valve CLOSED

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SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 OPERATING INSTRUCTION 5023-3-2.7 REVISION 7 PAGE 9 0F 9

(

ATTACHMENT 8.1 CHECK-0FF LIST 1 TCN 7-8 PERFORMED BY:

//m DATE/ TIME A[/$['(I /r5'f Op nitta s PERFORM'ED BY:

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OATE/ TIME d-/I M/

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t5F In"itTatr VERIFIED BY:

/ W DATE/ TIME 2 -/f'3I / /SSF Opera + r Initials VERIFIED BY:

DATE/ TIME F/5--h

/fW Operator Initials

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NOTE:

SRO Ops. Supv. shall not sign " Reviewed By" until all comments in relation to this Check-Off List have been resolved f.e.: TCNs written and incorporated, caps and flanges installed, locks and chains in place, etc.

l REVIEWED BY:

DATE/ TIME 2-/O'W l?YO 5 0 Ops. Supv.

FILE DISPOSITION: Fi per 5023-0-28

..r7 COMMENTS: $

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REV!5!ON 2CPERATING IN ATTACHMENT 2 PAGE 20 0F 28 PROCEDURE SIGNATURE SUPPLEMENT TCN 2-1 Sheet of A GECTED PROCEDURE:

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DEI 6 TOR /] NIT DATE/ TI ATTACHMENT 2 PAGE 1 0F 3