ML18089A248
| ML18089A248 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/14/1983 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18089A247 | List: |
| References | |
| AD-16, NUDOCS 8307270406 | |
| Download: ML18089A248 (21) | |
Text
SALEM GENERATING STA'J:'-ION OPERATIONS .DEPARTMENT DOCUMENT APPROVAL
~ -* COVER
~/
Title:
Post Reactor. Trip/Safety Injection Review 3
No.: AD-16 Unit:
- -..- 1/2
--- ..i:~ "";V *
- Remarks: eigh_~-~ag:=s of text, one - six page form, one - four page form, or1 *, - two page *_able 1 revised to add documentation for General Manager re~~e~, ~e~eted startup ap~roval requirements after controlle shutdown, deleted I&C Supervisor signature on Sequence of Events.
Sarety Related *Review (Ref. AD-13) S/R yes* x no - - - - - - - l Author's Checklist Completed: yes ___x_ _
Date/- !l-6 I
Date --12/f:
_,..-/ . C',
Date* -JZ-!Y sos+ ( ', I.
Date) 13 83 SORC ** S:3-9 c/ Date 7-/J- Y3
- _\' ) -~ J I I J/-~--
General Manager .:*)/ 1 1- L ~~-;.f,1--r:)_, i-:-c:=i Date 1/ 1 < .:1_.:;
- required for SPM documents only
+ required. for EOP validation acceptance only
- required!tiifor safety related documents and fire protection documents Salem Unit 1/2 AD-1-B-l MASTER r~n~J-~--~~1----~---------------~
f' -~.
- .--* .. --~, - --*-*---- --*-*- ---.-- - -*---- - -
ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR TRIP/SAFETY INJECTION REVIEW 1.0 PURPOSE The purpose of this directive is to establish the requirements to perform a formal post trip review for all Reactor Trip and Safety Injection events. This directive also establishes the requirements and criteria that must be rnnt oric~ +n thA star~up of either unit followin~ a ~rip event.
2.0 RESPONSIBILJ~IES
') .:
~*-* * ..l. In t~e event of ~ Reactor Trip or Safety Inj~~tion, the S':~.i.or Shift Supervisor shall:
2.1.1 Ensure that a post trip review of the event has been performed in accordance with the specific directions in Section 3.0 of this directive.
Form AD-16-A "Post Reactor Trip/Safety Injection Review Report" shall be used when performing this review. This report shall be completed and reviewed 0ith the appropriate management
, . . . 1 . . 1 ~ * '
- personne~~prior ~o _eaving ~ne ~~a~ion or requesting approval to startup the affected unit.
2.1.2 Contact the Instrumentation and Controls Engineer and request assistance for the review of the Sequence of Events print out.
2.1.3 Evaluate the post trip review to determine if:
a) All equipment and systems functioned as designed during the event.
b) The cause of the event is clearly identified.
2.1.4 Notify the Operations Manager of the event and the subsequent findings of the report. {The Operations Manager may elect to conduct this review by* telephohe in direct conference with the Senior Shift Supervisor.)
2.2 The STA qualified Shift Supervisor shall assist and advise the Senior Shift Supervisor in the compiling of data and evaluation of the report.
Salem Unit 1/2 1 ASTER Rev. 3
AD-16 2~3 In the event of a Reactor Trip or Saf~ty Injection, the Operations Manager shall:
2.3.1 Perform the following prior to granting approval for startup:
a) Review the post trip report with the Senior Shift Supervisor.
I b) Ensure that the report was properly prepared and evaluated.
I..
c) Ensure that the cause of tli~ event has been properly identified.
d) Ensure that all equipment and systems functioned as designed during the event and recovery actions.
e) Evaluate the event to determine if there are any corrective actions required prior to the startup of the affected unit.
f) As necessary, request additional technical support, to evaluate the event and ensure that the cause is clearly identified and the required corrective actions have been initiated.
2.3.2 Grant approval for startup in accordance with Section 4.0 of this directive if all of the requirements listed above are met satisfa~torily.
i* 2.3.3 Deny approval for startup if one or more of the I requirements listed above is not satisfactorily met. If this is the case, direct the Senior Operations Supervisor to conduct a further investigation of the event.
2.3.4 Perform a follow up review of the report and recommend any corrective actions. Conduct interviews as necessary to determine the effectiveness of the procedures used, this directive and, in particular, of the report itself. Note any changes which may enhance the conducting or the review of the report. Sign and date the Followup Section of the report.
2.3.5 Forward the completed report to the Senior Operations Supervisor for additional processing.
Salem Unit 1/2 2 ASTER Rev. 3
- . \ AD-16
\
2.4 The Senior Operations Supervisor shall:
2.4.1 Incorporate the event into the Reactor Trip/Safety Injection history trending system.
2.4.2 Make three complete copies of the report. These copies shall go to:
a) The Technical Department for assistance in preparing the Licensee Event Report or other reports as appropriate.
b) The General Manager Nuclear Support in order to conduct an independent review of the trip event.
c) The Manager - Nuclear Training for appropriate disbursement to the training classes.
2.4.3 Maintain* the original report on file for. future reference.
2.4.4 Conduct an investigation of the event if the Operations Manager denies startup approval.
Present the findings to the Station Operations
- Review Committee.
2.4.5 If approval for startup has been granted by the Operations Manager, present the report to the Station Operations Review Cormni ttee for review.
- 2. 4. 6 Prepare ct sum.rnary report on the event and issue it to all pertinent Operations Department personnel in accordance with the Information Directives System.
2.4.7 Revise this document as necessary to incorporate any co:mrnents on improving the effectiveness of it as directed by the Ope~ations Manager.
2.5 The Nuclear Support Department will perform an independent review of each Reactor Trip/Safety Injection. Upon completion of the review, Nuclear Support will make recommendations to the station for corrective actions which may prevent this type of event from re-occuring in the future.
Salem Unit 1/2 3 Rev. 3
AD-16 2.6 The Instrumentation and Controls Engineer will designate a supervisory person to assist the Senior Shift Supervisor and the STA qualified Shift Supervisor in the review of the Sequence of Events print out for each Reactor Trip/Safety Injection Event.
3.0 TRIP EVENT REVIEW PROCESS 3.1 The Senior Shift Supervisor shall ensure that:
I 3.1.1 The required information on Form AD-16-A I concerning the condition of the unit prior to the event is correct ;:__-_* -3_ has been recorded.
3.1.2 The evolutions in progress prior to the event that may be involved in the cause of event or could have contributed to the cause of the event have been recorded.
Examples:
- a. Unit startup was in ~rogress, feedwater control was in manual control.
- b. Unit startup was in progress, problems were encountered with inservice equipment or control systems. (Steam Dump was in manual, Steam Generator Feed Pump controls were in manual, Atmospheric relief valves were being used to dump steam, etc.).
- c. A rapid reduction in unit load was required due to loss of circulators, condenser vacuum, condensate pump, heater drain pu~p, condensate strainers were partially clogged.
- d. Surveillance testing was in progress on the Reactor Protection System.
- e. Maintenance or trouble shooting was in progress.
Salem Unit 1/2 4 MASTER
_\
AD-16 3.1.3 All equipment that was out bf service that could have contributed to the event has been identified and recorded.
Examples:
- a. Stearn Dumps were not available.
- b. Number llA and llB circulators were out of service.
- c. The positive displacement charging pump was Cleare~*and Tagged for repairs.
- d. Feedwatfur heater string was bypassed or out of service for repairs.
3.1.4 The proper classification of the event, the time that the event was declared, the time that the event was terminated, and if all the necessary notifications were made is documented in the report. Attach the original copy of the Emergency Procedure to the report package.
3.1.5 The P-250 computer sequence of events printout has been reviewed and the Seauence of Events Checklist (Form AD-16-B) has been completed to verify the cause of the event- and ensure that all equipment. and systems performed as designed and in the proper and expected s~quence~ The subsequent alarms listed on the Sequence of Events Checklist are not listed in the order in which they should occur; this will vary with the event. In addition, all of the alarms listed on the checklist might not occur with every event.
Table 1 contains the expected times at which the Subsequent alarms should print out. It should be noted that the times are only approximate and will be further refined as experience is gained.
Attach the computer printout to the report package.
Salem Unit 1/2 5 ASTER Rev. 3
AD-16 3~1.6 The following control room recorder charts have been reviewed for unexpected or unusual parameter changes during the event:
- a. Steam Generator Narrow Range Levels LA-5048, LA-5049, LA-5050, LA-5051
- b. Pressurizer Level LA-5304
- c. Pressurizer Pressure PA-5305
- d. TAVE TA-5306
. t .
- e. Reactor Coolant Loop Th, Tc TA-0014, TA-0016, TA-0036, TA-0038
- f. Nuclear Power Range NR-45 XA-5904
- g. Other charts as necessary Have the Shift Technician remove these charts.
Ensure that all tracings are identified on the charts and the time is clearly marked. Attach the original charts to the report package.
3.1.7 Any alarms received which were out of the ordinary for the event and alarms which should have been received but were' not have been recorded. Include a review of the overhead alarms, console alarms, P-250 alarms and the Auxiliary Alarm typewriter. Attach the printout from the Auxiliary Alarm typewriter and the P-250 alarm printout.
3.1.8 Fact finding sessions are conducted with the appropriate personnel to determine the cause of the event, actions taken and observed sequence of events.
3.1.9 The explanation of the cause of the event is recorded.
3.1.10 The corrective actions taken during the event to mitigate the consequences of the event and bring the unit to a stable condition are recorded.
3.1.11 Any equipment out of service which would prevent the unit from being returned to service has been recorded.
Salem Unit 1/2 6 MASTER Rev. 3
AD-16 3.1.12 All~echnical Specification or Adminstrative Actipn Statements that are required to be term~nated prior to reactor startup have been recorded. (Administrative Action Statements as identified in other Operations Department Directives, such as defined in OD-12.)
3 .1. l3 Any corrective actions that are required r, '-,.-,-~ :*,- '
the unit's return to service are recorded. -~ _-~ J
. , ... I 3 1 14
- i~~i ~~~~!1 :n~n~~ ~ ~~~e~/~~! t!~~~ t 0
!r:1~ec '5rcle;: .*..*...*. I..
3.2 The Senior Shift Supervisor shall confer with the S~~
qualified Shift Supervisor in order to review and evaluate the report. When both are satisfied with the conclusions, each shall sign and date the report.
3.3 The Operations Manager shall he briefed by the Senior Shift Supervisor on the report. At that time, a determination shall be made as to whether approval should be granted for startup as defined in Section 4.0 of this directive.
4.0 APPROVAL REQUIREMENTS FOR REACTOR STARTUP AFTER A REACTOR TRIP/SAFETY INJ~CTION 4.1 Prior to requesting approval to startup the reactor after any Reactor Trip or Safety Injection, the Post Trip Review must be completed and evaluated.
4.2 Upon satisfactory completion of the review*and evaluation of the Post Trip Review, the Operations Manager may authorize the reactor startup as long as the evaluation of the trip event clearly indicates the cause of the event and that all equipment and systems functioned as designed.
4.3 If the Operations Manager-Salem Operations is not available, then the individuals who are authorized to assume the Operations Manager 1 s responsibilities mav authorize the reactor startup.
Salem Unit.1/2 7 Rev. 3
AD-16 4.4 If the cause of the event has not been clearly determined or there is question concerning the proper performance of equipment or systems during the event, then an investigation shall be conducted and the results of the investigation shall be reviewed by the Station Operations Review Committee. Upon completion of the evaluation of the event by the Station Operations Review l.r:nn.rni ttee, the Committee shall make recomn.'~- . ::..:...i-:_.::,.:~, :____:
the General Manager-Salem Operations on reactor startup.
Upon completion of the review and satisf~~t~~y determination that the unit can be resta* -c_ed safely, -r-*_1e General Manager*-Salem Operations may* authl*rize *the i::-eactor startup.
E*~JD OF PROCEDURE FINAL PAGE Salem Unit 1/2 8 Rev. 3
ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR TRIP/SAFETY INJECTION REVIEW REPORT CONDITIONS PRIOR TO EVENT Date of Event Time of Event Affected Unit
~ -----
Unit Conditions Prior to the Event Reactor Power %
~--=-=-------------
Bo a rd NCO D e_s_k_r;_JC -::------------~ ----
Prirrlary *Eo Secondary EO SS ups ______________ _ Shift Tecr11~_l_c_i_a-_-n-.-
Others Shift Electr:~ ,:~:*.~-~ ------
~
(Relay. Dept., I&C, Maint., Maplewood Lab etc.)
What evolutions were in progress at the onset of the event:
Surveillance Testing Yes No - - -
Trouble Shooting or Maintenance Yes No - - - -
Unit Startup or Shutdown Activities Yes No Other Activities which could have contributed to the _e_v_e_n_t_
Yes No If the answer to any of the above questions is yes, describe the circumstances in detail.
Were any of the following out of service or inoperable at the onset of the event:
Major Equipment Yes - - - - No - - - -
Protection Systems or Trains Yes - - - - No Control Systems Yes - - - - No If the answer to any of the above questions is yes, describe the circumstances in detail.
Salem Unit 1/2 AD-16-A-1 MASTER Rev. 3
DESCRIPTION OF THE EVENT Reactor Trip Initiation Automatic Yes No
---=-- ---~
If no, explain why. If yes, give the Reactor First Out Annunciator Safety Injection Initiated Yes
--- No - - * - -
If initiated, was it automatic Ves . No If no, explain why. If yes, giv~ thP P~actor - - - -Out First Annunciator.
Attach ATT 1-1 from EI I-4.2 if Safety Injection occured.
What is the classification of the event as defined in EP I-0?
Time Declared Time Terminated Were all of the required notifications made?
Yes No If no, explain why.
Attach Emergency Procedure to Report Package.
Does the Sequence of Events Printout from the P-250 agree with the Reactor First Out Annunciator which was received?
Yes No If no, explain which First Out was received and any apparent reasons for the discrepancy. ( eg. Two alarm conditions actuated simultaneously)
Attach Printout to Report Package.
Do the recorder charts indicate any trends which may have contributed to the event?
Yes No If yes, explain in detail.
Attach Recorder Charts to Report Package.
~1ASTtR
~!~.
{-
~J ..{:J*
- Salem Unit 1/2 AD-16-A-2 . L 1.\ . Rev. 3
Were there any alarms which annunciated which were unusual for the event?
Yes No If yes, explain in detail.
Were there any alarms which shoui~ hav~ annucia~ed but did not?
Yes No - - - -
If yes, explain in detail.
Explain in detail the sequence of events which led to the initiation of the event and the actions performed to place the plan in a stable condition. Include the observations and actions of specific individuals and the adequacy of the procedures used.
Attach additional pages as required.
Salem Unit 1/2 AD-16-A-3 MASTER Rev. 3
.\ .
- i
-CORRECTIVE ACTIONS Is there any equipment out of service which would prevent the unit from being returned to service?
Yes No ---~
If yes, explain in detail.
Are there any Technical ~~~cification ~r Administrative Action Statements in effect whic11 *:~,vould p.rr~vent the unit from returning to service? (Administrati~e .~ction Statements are described in OD-12 or other Operations Del~~~~~Dt documents)
Yes No - - - -
If yes, list below.
Tech Specs Admin.
~
Are there any corrective actions which should be performed before returning the unit to service, such as repairs which should be made?
Yes No- - - -
If yes, explain. Provide specific recowmendations as appropriate.
Report Prepared By Date Time
~
Report Reviewed With Operations Manager Date - - - - - - Time - - - -
Approval for startup by Operations Manager:
Granted Denied Date Time - - - -
STA Qualified Shift Supervisor Date Time (Signature)
Senior Shift Supervisor Review Date - - - - - - Time - - - -
(Signature)
ASTER
/
Salem Unit 1/2 AD-16-A-4 Rev. 3
i SORC AND GENERAL MANAGER REVIEW ***~*
This page will be used only when the initial approval for startup i~
denied by the Operations Manager and subsequent reviews of the event are required.
MAJOR FINDINGS OF SUBSEQUENT INVESTIGATIONS Attach other sheets as necessary.
DETEPJ1INATIONS BY SORC Attach other sheets as necessary.
STARTUP APPROVAL SORC Chairman Date General Manager-Salem Date Salem Unit 1/2 AD-16-A-:-5 ASTER Rev. 3
OPERATIONS MANAGER FOLLOWUP Corrective actions required to prevent reoccurrence of this event .
- -l-Note any changes to this document which may improve l L. s effectiveness Report Reviewed By Operations Manager Date Time - - - - -
~------~
(signature)
NOTE: This review is not required prior to authorizing startup.
SENIOR OPERATIONS SUPERVISOR FOLLOWUP Copies of. the report sent to:
Technical Department Date
~
Nuclear Support Department Date
~
Nuclear Training Department Date - - - - - -
~-------------
Station Operations Review Committee Review Chairman Meeting .No. - - - - - - Date Salem Unit 1/2 AD-16-A-6 Rev. 3
~EQUENCE OF EVENTS CHECKLIST DIRECTIONS The information to be recorded on the Sequence of Events Checklist (pages AD-16-B-2 and AD-16-B-3) is to be a direct transfer of information from the Sequence of Events print out. Simply record the number of cycles at which the subsequent alarm occurred and the Sequence of Events start time in which it occurred.
The SUD!='.80UP.nt o. 1 arms 1 isted on the Sequence of Events c:::-:,s::::~:~ist must be related to the initial Reactor Trip or Safety Injection signal ~qs0c~0~ 0 1 .-~ith each trip. To perform this, the following guidelines shou~d ~~ used.
- 1. If the subsequent alarm occurred in the same sc~uence as
~h~ ~aactor Trip or Safety Injection signal, simply subtract the number of cycles at which the Reactor Trip or Safety Injection signal was generated from the number of cycles at which the subsequent alarm was generated.
- 2. If the subsequent alarm occurred in a sequence separate from the Rea~tor Trip or Safety Injection signal, perform the following:
- a. Subtract the Reactor Trip or Safety Injection signal sequence start time from the subsequent alarm sequence start time and multiply this number by 60.
- b. From this number, subtract the number of cycles at which the Reactor Trip or Safety Injection signal was generated.
- c. To this number, add the number of cycles. at which the subsequent alarm was generated. This is the number of cycles at which the alarm was generated after the Reactor Trip or Safety Injection signal.
This information shall be recorded on page AD-16-B-4.
Salem Unit 1/2 AD-16-B-l MASTER Rev. 3
\
SEQUENCE OF EVENTS CHECKLIST Reactor Trip or Safety Injection signal sequence start time:
REACTOR TRIP SIGNAL INITIATED AT
- - - - - - - - - -cycles SAFETY INJECTION SIGNAL INITIATED AT
- - - - - - -cycles sequence start I Ji 1t cycles t ir.. _; in which alarIT' Su_'1scq*-:cn~ _.t Alarms into sequence Illas initiated
~
REACTOR MAIN TRIP BKR A TRIP : :
RE.P.CTOR r-<lAIN TRIP BKR B TRIP :
REP..CTOR TRIP AUXl BKR .A. TRIP :
REACTOR TRIP AUXl BKR B TB.IP :
REACTOR r1Li\N TRP l TRIP :
REACTOR J:v""J.AT:~ TRP 2 TR.1P :
TURBINE STOP VA 11 ( 21) CLOSED :
TURBINE STOP VA 12 ( 2 2) CLOSED :
TURBINE STOP VA. 13 (23) CLOSED :
rr'URBINE STOP VA 14 ( 24) CLOSED :
TURBINE TRJ.P TB.IP :
rr'URBINE REMOTE EMERG TRJ.P TRIP :
Salem Unit 1/2 AD-16-B-2 Rev. 3
sequence start
- cycles time in which alarm Subsequent Alarms into sequence was initiated 11 (21) AUX FW PUMP START :
112 (22) AUX FW PUMP START I :
F-11 ( 21)
) AUX FW PUMP TURBHTE STOP VA NT CL SGFP TURBINE HRH STOP VA CLOSED :
12 (22) SGFP TUF.BINE MS STOP VA CLOSED :- -:
12 ( 22) SGFP TURBINE HRH STOP VA CLOSED :
11 (21) SGFP TUR.BI NE .MS STOP VA CLOSED :
Salem Unit 1/2 AD-16-B-3 ASTER Rev. 3
SEQUENCE OF EVENTS CHECKLIST
SUMMARY
number of cycles after Subsequent Alarms Reactor Trip/SI signal REACTOR MAIN TRIP BKR A TRIP l.K.t;ACTOR MAIN TRIP BKR B TRIP IREACTOR TRIP AUXl BKR A TRIP REACTOR TRIP AUXl BKR B TRIP REf._CTOR MAN TRP 1 TRIP REACTOR MAN TRP 2 TRIP TUEBINE STOP VA 11 (21) CLOSED I rrURBI~1E STOP VA 12 ( 22) CLOSED TURBINE STOP VA 13 (23) CLOSED TURBINE STOP VA 14 (24) CLOSED TURBHTE TRIP TRIP TURBINE REMOTE EMERG TRIP TRIP 11 ( 21) AUX FW PUMP START 12 {22) P..UX FW PUMP START 13 (23) AUX FW PUMP TURBINE STOP VA NT CL 11 (21) SGFP TURBINE HRH STOP VA CLOSED 12 ( 22) SGFP TURBINE MS STOP VA CLOSED 12 ( 22) SGFP TURBINE HRH STOP VA CLOSED 11 (21) SGFP TURBINE MS STOP VA CLOSED
~M-A~Tif" 0 Salem Unit 1/2 AD-16-B-4 ~ ii : ;
- tn Rev. 3
l AD-16 SEQUENCE OF EVENTS STANDARDS FOR A REACTOR TRIP Expected time to initiate after trip siqnal Subsequent Alarms cvcles seconds REACTOR MAIN TRIP BKR A TB.IP 4-6 0.06-0.1 REACTOR .tv'l..AIN TRIP BKR B TRIP 4-6 0.06-0.1 REACTOR TRIP AUXl BKR A TRIP 4-6 0.06-0.1 REACTOR TRIP AUXl BKR B TRIP 4-6 0.06-0.l REACTOR .iYlAN TRP 1 TRIP less than 300 less than 5 REACT OP, M:AN TRP 2 TRIP less than 300 less than 5 TURBINE STOP VA 11 (21) CLOSED less than 90 less than 1. 5 TUEBINE STOP VA 12 (22) CLOSED less than 90 less than 1. 5 TURBINE STOP VA 13 ( 23) CLOSED less than 90 less than 1. 5 TURBINE STOP VA 14 (24) CLOSED less than 90 less than 1. 5 IT URBINE TP.IP TRIP 4-6 0.06-~.1 TURBINE REI10TE EMERG TRIP TRIP less than 60 less than 1 11 (21) AUX FW PUMP START
- 12 ( 22) AUX FW PUMP START
- Should initiate within 10 cycles (0.2 sec) after any l Steam Generator Lo Lo Level valid trip signal.
- Should initiate within 100 cycles (1.7 sec) after any 2 Steam Generator Lo Lo Level valid trip signals.
Salem Unit 1/2 TABLE 1-1 ~1ASTER Rev. 3
. ~ .. AD-16 f SEQUENCE OF EVENTS
\
STA~lDARDS FOR A SAFETY INJECTION Expected time to initiate after SI siqnal Subsequent Alarms cycles seconds REACTOR MAIN TRIP BKR A 'J'lHP 4-6 0.06-0.1 REACTOR MAIN TRIP BKR B TRIP 4-6 0.06-0.1 I i ~
!REl1.CTOR TRIP 1rnx1 BKR A TRIP 4-6 0.06-0.1 1:
iREACTOR TRIP AUXl BKR B TRIP 4-6 0.06-0.1 111 ( 21) AUX FW PUMP START less than 10 less than 0.2 I, 2 , ~?.
.L \,:_) AUX FW PUMP START less than 10 less than 0.2 REACTOR i'v:!AN TRP 1 TRIP less than 300 less than 5 REACTOR MAN TRP 2 TRIP less than 300 less than 5 I' URBINE STOP VA 11 ( 21) CLOSED less than 90 less than 1. 5 TURBINE STOP V".!cl 12 (22) CLOSED less than 90 less than 1. 5 TU EB I NE STOP VA 13 (23) CLOSED less than 90 less than 1. 5
'I' URBINE STOP VA 14 (24) CLOSED less than 90 less than 1. 5 rr'URBINE TRIP TRIP 4-6 0.06-0.1
'I'URBINE REMOTE EMERG TRIP TRIP less than 60 less than 1
( 21) 11 SGFP TURBINE HRH STOP VA CLOSED less than 90 less than 1. 5
{2 2) 12 SGFP TURBINE HRH STOP VA CLOSED less than 90 less than 1.5
( 21) 11 SGFP TURBINE MS STOP VA CLOSED less than 90 less than 1. 5
( 2 2) 12 SGFP TURBINE MS. STOP VA CLOSED less than 90 less than 1.5 13(23) AUX FW PUMP TURBINE STOP VA NT CL *
- Should initiate within 100 cycles (1.7 sec) after any 2 Stearn Generator Lo Lo Level valid trip signals.
Salem Unit 1/2 P.ev. 3