Text

Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection
	ML18101A675
Person / Time
Site:	Salem
Issue date:	02/16/1995
From:	Beattie J; Public Service Enterprise Group
To:	;
Shared Package
ML18101A674	List: ML18101A673; ML18101A675; ML18101A676; ML18101A677;
References
	1-EOP-TRIP-1, NUDOCS 9505020322
	Download: ML18101A675 (15)
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SALEM OPERATIONS l-EOP-TRIP-1, Rev. 11

REACTOR TRIP OR SAFETY INJECTION USE CATEGORY: I REVISION

SUMMARY

The following changes are editorial (Revision Bars were not utilized for this change):

Step 21 on sheet 2 has been changed to remove the action steps which manipulated the MSlO controls.

These controls were enhanced in DCP tEC-3325 and remote board operation is no longer required to remove the "reset and windup" within the valve controller.

Step 42 on sheet 4 bas been changed to update this procedure to the Tech. Spec. Amendment which altered our SIG Lo-Lo Trip setpoint. The setpoint was changed to 9% and affects our AFW Interlock.

Step 42 has been revised as follows:

ESTABLJSH SG NR LEVELS SUCH THAT ALL SG Lo-Lo LEVEL BISTABLES ARE """RisET AS INDICATED BY:

1RP4 OBA BEZEL INDICATION On sheet J and 4 oftbe Continuous Action Summary under the requirements to go to 1-EOP-FRTS-1 a "Typo correction" to change the 240 °F to 280°F. This is the required temperature in Unit One CFSTs.

IMPLEMENTATION REQUIREMENTS:

hsue of Information Directive 95-004

~~*

APPROVED: ___

O_P._'E.~'.RA-T.-1o

__ w._."S.._~~--r-F._'.R DATE: t. -)/-fr r~-~9::5=-0=5~0-=2:-::0:::::3:::2:::2~9=5=-----0--:4-2-1-,-* -~\\

PDR ADOCK 05000272 I

s PDR I

TABLEl CONTINUOUS ACTION

SUMMARY

CONDmON RCS PRESSURE LESS THAN 1355 PSIG AND SI FLOW ESTABLISHED SINGLE SG FAUL TED OR RUPTURED RCS PRESSURE LESS 1HAN 1500 PSIG AND BIT FLOW ESTABLISHED RCS PRESSURE GREATER THAN 2000 PSIG LESS THAN TWO VITAL BUSES ENERGIZED RCPs WITHOUT CCW AFST LEVEL LESS THAN 14%

TWO OR MORE POWER RANGES GREATER THAN 5%

5 OR MORE CORE EXIT TCs GREATER TIIAN 1200 °F 5 OR MORE CORE EXIT TCs GREATER THAN 700 °F AND RVLIS FULL RANGE LESS THAN 50%

ALL SG NR LEVELS LESS THAN 8% (12% ADVERSE)

AND TOT AL FEED FLOW CAPABILITY TO SGs LESS THAN 22E04 LB/HR SALEMUNITt TABLEt-1 EOP-TRIP-1 ACTION STOPRCPs CLOSE AFI 1 AND AF21 FOR AFFECTEDSG CLOSE CHG PUMP MINIFLOW OPEN CHG PUMP MINIFLOW GO TO EOP-LOPA-1 STOPRCPs SHIFT AFWPUMP SUCTION GO TO EOP-FRSM-1 GO TO EOP-FRCC-1 GO TO EOP-FRHS* l REV.11

TABLEl CONTINUOUS ACTION

SUMMARY

CONDITION RCS COOLDOWN GREATER TIIAN 100 °F IN LAST 60 MIN AND RCS COLD LEG TEMPERATRUE LESS THAN 280 °F CONTAINMENT PRESSURE GREATER THAN 47 PSIG SALEMUNITl TABLE 1-2 EOP-TRIP-1 ACTION GO TO EOP-FRTS-1 GO TO EOP-FRCE-1 REV.11

EMERGENCY OPERATING PROCEDURE EOP-TRIP-1 REACTOR TRIP OR SAFETY JNJECTION 1.0 Entry Conditions 1.1 Initiate this procedure when a Reactor Trip is required (Step 1.1.l} or has occurred (Step 1.1.2):

1.1.1 Reactor Trip is required by~ of the following:

Any Reactor Trip OHA AND associated bistable coincidence on 1RP4.

+ OHA A-34 AND A-42 lit (SSPS Trouble).

OHA F-36 lit (Turbine Trip and P-9) AND associated bistable coincidence on 1RP4.

1.1.2 Occurrence of a Reactor Trip is confirmed by both of the following:

IRPI indicates rods are inserted OR Gamma Metrics neutron flux decreasing.

One or more of the following occur:

Reactor Trip light on 1RP4 illuminated.

OHA F-40 lit (Reactor Trip).

Reactor Trip breaker AND associated Bypass breaker open.

1.2 Initiate this procedure when Safety Injection is required (Step 1.2.1) or has occurred (Step 1.2.2):

1.2.1 Safety Injection is required by any SI First Out OHA AND. associated bistable coincidence on 1RP4.

1.2.2 Occurrence of a Safety Injection is confinned by SI Actuation as indicated on 1RP4 equipment status.

2.0

Operator Actions 2.1 Immediate Actions See Flowchart 2.2 Subsequent Actions See Flowchart SALEM UNIT I Page 1 REVU

3.0 Attachments List 3.1 Tables EMERGENCY OPERATING PROCEDURE EOP-TRIP-1 REACTOR TRIP OR SAFETY INJECTION CAS TABLE 1-1 3.2 Fi~ures None 3.3 Graphs None 3.4 Check Off Sheets None End of Procedure Final Page SALEMUNITt Page 2 REVll

PAGE CHANGE CONTROL SHEET List of Pages 1-EOP-TRIP-1 SHEET1 Rev. 11 1-EOP-TRIP-1 SHEET2 Rev. 11 1-EOP-TRIP-1 SHEETJ Rev.11 l-EOP-TRIP-1 SHEET4 Rev. 11 1-EOP-TRIP-l CAS TABLE 1-1 Rev.11 SALEM UNIT I Page 3 REVU

SC.OP-DD.ZZ-AD44{Q)

ATTACHMENT 1 EOP CHANGE REQUEST DISPOSITION FORM Procedure Number:

l-EOP-TRIP-1 Date Received:

8 Feb. 1995

~-----------------------

Procedure

Title:

REACTOR TRIP OR SAFETY INJECTION EOP Change Request Number Assigned:

95-001 Disposition:

1. The change request:

~ a) warrants a change D b) does not warrant a change (see comments)

D c) requires further research (see comments)

2. If a change is warranted, it will be made:

[8J a) immediately (within two weeks)

Db) when the next full revision is made to the procedure (see comments)

D c) prior to full revision (see comments)

3. Training requirements:

1:8:1 a) Information Directive D b) Shift Briefing D c) Simulator Session Comments:

First, I-BOP-TRIP-I is being revised to remove the steps which manipulate the MSlO controls. These controls were enhanced in DCP lEC-3325 and remote board operation is no longer required to remove the "reset and windup" within the valve controller. Second, Tech. Specs. have been amended changing the SIG Lo-Lo Trip setpoint which affects the AFW Interlock I SIG sample valves.

Prepared:

Jeff Beattie~

Date:

c=ro"'="'w~-:--o=p~c~oord--,,-inal_oc_) ____ --+:1-----------------

9 Feb. 1995 Verified:

Date:

~___,.,,__(OperatiD=---:.,:;.g--=E~ngui-:--, -ce....,.r ) __

_::__=:....;;..~"""'-"~"-4'-=-------_==----

---=--.

Salem Common Page 65 of91 Rev.1

SC.OP-DD.ZZ.AD44(Q)

ATIACHMENT 2 EMERGENCY OPERATING PROCEDURE APPROVAL COVER PAGE Procedure Number:

1-EOP-TRIP-1 Procedure

Title:

REACTOR TRIP OR SAFETY INJECTION Unit Number:

1 Revision Number:

11 Remarks:

The following changes are editorial (Revision Bars were not utilized for this change):

Step 21 on sheet 2 has been changed to remove the action steps which manipulated the MSlO controls.

These controls were enhanced in DCP IEC-3325 and remote board operation is no longer required to remove the "reset and windup" within the valve controller.

Step 42 on sheet 4 has been changed to update this procedure to the Tech. Spec. Amendment which altered our SIG Lo-Lo Trip setpoint. The setpoint was changed to 9% and affects our AFW Interlock.

Step 42 has been revised as follows:

ESf ABLJSH SG NR LEVELS SUCH THAT ALL SG Lo-Lo LEVEL BISTABLES ARE RFJIBT }.S INDICATED BY:

1RP4 OHA

BEZEL INDICATION

REVIEW I APPROVAL------------

SOTS: --~~~~:::::::~~~~=======--- Date: cJ.,td/;r Senior Reactor Operator:

~

---.-+~...,!_::.::...._~=:::;::::==:::...._-- Date:

c.

1 J 7

n Operating Engineer: --~--------------- Date:

Yt*>-li~../

Salem Common Page 66 of 91 Rev. 1

SC.OP-DD.ZZ-AD44(Q)

ATTACHMENT 3 EDITORIAL VERIFICATION FORM Evaluator (SRO): ___

.:....::.Q_. _C_-::i_J *

.;...z...._1

-;.:;;;....~_} _________ Date:

Procedure Number:

1-EOP-TRIP-1 Draft Rev.

11

~~~~~~~~~~~~~~~--~

Procedure

Title:

REACTOR TRIP OR SAFETY INJECTION VERIFICATION CRITERIA DISCREPANCY NUMBER

1. Legibility

2. Format Consistency

3. Identification Information

4. Information Presentation

5. Procedure Referencing NOTE For each discrepancy, a Verification Discrepancy Sheet (Attachment 4) is required to be filled out and attached to this form.

Evaluation Complete:

Discrepancies Resolved and Incorporated:

Editorial Verification Form I Resolutions Reviewed:

Salem Common L *

( Evaluator Sign I Date )

Page 67 of91 Rev. l

SC.OP-DD.ZZ-AD44(Q)

Procedure Number:

Draft Revision:

11 ATTACHMENT 5 TECHNICAL VERIFICATION FORM l-EOP-TRIP-1 Procedure

Title:

REACTOR TRIP OR SAFETY INJECTION Eva1uator(s): __

p=-~: __

o'--.* ~--* ~-------------------

Scope of Verification:

Full Partial ( specify steps or sections )

TABLE TOP V&V. Verify the bullets listed under the REVISION

SUMMARY

. Follow the guidance provided in SC.OP-DD.ZZ-AD44(Z) Sections 7.0 & 10.5.

VERIFICATION CRITERIA DISCREPANCY NUMBER I) Source Documents

2) Quantitative Values

3) Plant Hardware

4) Conformance Items NOTE For each discrepancy, a Verification Discrepancy Sheet (Attachment 4) is required to be filled out and attached to this form.

Li' 1

. /d

2 1})~*.r;}.

Evaluation Complete:

/

1...., Lr** L---

C-t"Evaluator Sign I Date)

Discrepancies Resolved and Incorporated:

Technical Verification Form I Final Resolutions Reviewed:

Salem Common

£ Q)

'/

~-**,... CJ:--.

-"L,

( Operating Engineer Sign I Date )d Page 69 of91 Rev. I

SC.OP-DD.ZZ-AD44(Q)

Procedure Number:

ATTACHMENT 6 TECHNICAL VALIDATION FORM 1-EOP-TRIP-1 Procedure

Title:

REACTOR TRIP OR SAFETY INJECTION Draft Revision:

11 Validation Method:

TABLE TOP

~

~-------------

Validation Scope:

Verify the bullets listed under the REVISION

SUMMARY

. Follow the guidance provided in SC.OP-DD.ZZ-AD44(Z) Sections 7.0 & 10.5.

Plant Operations Personnel:

£. Cll,,,J Qualifications (SRO, RO etc.)

~sLD Validation team Members Organiz.ation and Title Ops-BOP I ADP CoordinatOT Ops-SRO A-NOTE For each Discrepancy, a Verification Discrepancy Sheet (Attachment 7) is required to be filled out and attached to this form.

Validation Exercise Completed:

Discrepancies Resolved and Incorporated:

Validations and Resolutions Reviewed and Approved:

Salem Common oordinator Sign I Date )

( EOP I AOP ordinator Sign I Date )

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-~/

(

I:..

C.J

/T...,* -

"-f *-

_L,

( Opecltlng Engineer Sign I Date )

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ML18101A675

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