ML18087A727

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Post-Reactor Trip/Safety Injection Review.
ML18087A727
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/14/1983
From:
Public Service Enterprise Group
To:
Shared Package
ML18087A720 List:
References
AD-16, NUDOCS 8303160505
Download: ML18087A727 (26)
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Text

SALEM GENERATING STATION OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET

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Title:

Post Reactor Trip/Safety Injection Review and Unit Startup Approval Requirements No.: AD-16 Unit: 1/2 Rev.: 0 Remarks: Initial issue. Six pages of text, one- four page form.

Safety Related Review (Ref. AD-13) : S/R yes x no Author's Checklist Completed: yes x

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y;~/&.!>

Author Date ~~~~

' I SRO

  • NLA ,ft_ Date 3/3/83 Ops. Eng.

SOS+ N/A,"4 r -

)J~ Date 3/J/8'J Date 3/3/83

-Ops. Mgr. 1~ -- ~f j- Date 3h /'5'J

/ /

QA

    • Q.e ~~ Date .; /3/8..2>

I '

SORC ** ~.f>.12~~-fd. Date 3h/"'3 General Manager** ,l/J2 ~ Date 3/3/!'3 .

  • required for SPM*documents only

+ required for ~OP validation acceptance only

_-. **. ~~guired for safety related documents and fire protection documents

~

8303160505 830314 PDR ADOCK 05000272 I I

S PDR MASTER I Salem Unit 1/2 AD-1-B-1 Rev. 4

DOCUMENT INITIATION/REVISION CHECKLIST

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DOCUMENT TITLE:

DOCUMENT NUMBER

UNIT _____

1/t.- REV o Section A - Pre-review Checks (to be completed by author)

1. Document initiated/revised IAW AD-2
2. Document typed IAW AD-4
3. Refer to AD-14 to reference any procedures which may be affected by this revision.

Affected procedure(s) _____M_rh_______________________

4. If this document generates records, do they have to be added to AD-3 Section 8.0 yes ,/ no
s. Document reviewed with AD-13 for S/R stay;*

Must this procedure be.added to AD-13 es

--no

6. All applicable OTSCs incoq,orated and referenced on cover sheet (SPM only)
7. For EOPs which require Engineering Department verification/documentation of quantitative values, ensure Engineering has provided the values used in the procedure.
8. For *EOP procedure validation, check the method recommended. Real Performance Walk-Through Paced Simulator Performance ---

Table-Top_

9. .All vertical lines are drawn (if applicable)
10. Document reviewed for ID necessity IAW AD-18.

ID nee es sary / yes no *

11. Cover Sheet verified to be from current AD-1, and revision number has been whited-out.
12. Cover sheet completed and signed by. author

!t ~--,..~

Salem Unit 1/2 AD-1-C-l N~ 1~ * '\..

i\~ * .,_ .. ii. Rev. 4

Document Number ,l'i::::i.-1/,

~---~~~~~~~

Rev. Q Section B - Post Approval Checklist The following i~ems are to be completed by the author:

l. Verify TRIS Data Base reflects valve positions as per procedure revision.
2. ID written (if necessary)
3. If a procedure(s) is listed in Step A-3 of this checklist, submit a revision request to the Senior op*erations Supervisor for the affected procedure ( s) *.
4. If Step A-4 indicates an addition to AD-3, submit a revision request to the Senior Operations Supervisor.
5. If Step A-5 indicates an addition to AD-13, submit revision request to the Senior Operations Supervisor.

The following items are to be completed by the Administrative Coordinator:

6. If ID was written, record the following:

ID number Date ~~~~~~~~

7. If this*procedure replaces an existing procedure, and the existing procedure is referenced in the Inspection Order System, ensure that the existing procedure number is removed from the IO system and this procedure's number replaces it.

B. The procedure has been distributed in accordance with AD-3, and the Red Master is in its appropriate file. Date of completion ~~~~~~~~~~~~-

    • Salem Unit 1/2 AD-1-C-2 MASTER / Rev. 4

ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR .TRIP/SAFETY INJECTION REVIEW and STARTUP APPROVAL REQUIREMENTS 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 met prior to the startup of either unit following a trip event or upon return of the units after outages.

2.0 RESPONSIBILITIES 2.1 In the event of a Reactor Trip or Safety Injection, the Senior Shift Supervisor shall ensure that:

2.1.1 A post trip review of the event has been performed in accordance with the specific directions in Section 3.0 of this directive.

This report shall be completed prior to shift turnover.

.:. 2.1.2 2.1.3 The post trip review is evaluated to determine if all equipment and systems functioned as designed during the event and the cause of the event is clearly identified.

Form AD-16-A, Post Reactor Trip/Safety Injection Report is completed, signed and reviewed with the appropriate management personnel prior to leaving the Station or requesting approval to startup the affected unit.

2.2 In the event of a Reactor Trip or Safety Injection, th~

Operations Manager shall:

2.2.1 Review the post trip report with the Senior Shift Supervisor. _(The Operations Manager may elect to conduct this review by telephone in direct conference with the Senior Shift Supervisor.)

2.2.2 Ensure tha~ the r~port was properly prepared and evaluated.

2.2.3 Ensure that the cause of the event has been properly identified.

2.* 2. 4 Ensure that all equipment and systems functioned as designed during the event and recovery actions.

Salem Unit 1/2 1 Rev. 0

AD-16 2.2.S Evaluate the event to determine if there are any corrective actions required prior to the startup of the affected unit.

2.2,6 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.

2.2.7 Forward the completed report to the Senior*

Operations Supervisor for additional processing.

2.3 The Senior Operations Supervisor shall:

2.3.1 Incorporate the event* into the Reactor Trip/Safety Injection history trending system.

2.3.2 Maintain the original report on file for future reference.

2.3.3 Prepare a summary report on the event when requested to do so by the Opera~ions Manager.

. 2.3.4 2.3.S Obtain the Operations Manager's approval of the summary report and distribute the report as directed.

Forward copies of all pertinent information and a copy of the Post Trip Review Report to the Technical Department to assist in the preparation of the Licensee Event Report or other reports as appropriate.

3.0 TRIP EVENT REVIEW PROCESS 3.1 The Senior Shift Supervisor shall ensure that:

3 .1.1 The requir.ed information on Form AD-16-A concerning the condition of the unit prior to the event is correct and 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 *
  • Salem Unit i/2 2 Rev. 0

Examples:

a. Unit startup was in progress, feedwater control was in manual control.
b. Unit startup was in progress, pr*oblems were enconntered with inservice equipment or control systems. (Steam Dump was* in manual,.

Steam Generator Feed Pump controls were erratic, Atmospheric relief valves were being used to dump steam, etc.).

I *

c. A rapid reduction in unit load was required due to loss of circulators, condenser vacuum, condensate pump, heater drain pump, condensate strainers were partially clogged.
d. Surveillance testing was in progres*s on the*

Solid State Pro~ection System.

e. Maintenance or trouble shooting was in progress.

i.

3.1.3 All equipment that was out of service that could have contributed to the event has been identified and recorded.

Examples:

a. Steam Dumps were not available.
b. Number llA and llB circulators were out of service.
c. The positive displacement charging pump was Cleared and Tagged for repairs.
d. Feedwater heater string was bypassed or out of service for repairs.

Salem Unit 1/2 3 Rev. 0

AD-3.1.4 The computer sequence of events print out has been reviewed to verify the cause of the event and that all equipment and systems performed as designed and in the proper and expected sequence.

(Attach the printout to the form)

  • 3.1.5 All control room recorder charts have been reviewed for unexpected or unusual parameter changes during the event. (Attach appropriate recorder charts or copies of the charts to the form. Ensure all tracing are identified on the chart and the time clearly marked).

3.1.6 All alarms which were received which were out of the ordinary for the event and alarms which should have been received but were not have b.een 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.)

  • 3.1.7 Fact finding sessions are conducted, as required, with the appropriate personnel to determine the cause of the event., actions taken and observed sequence* of events.

3.1.B The explanation of the cause of the event is recorded.

3.1.9 The corrective actions taken during the event to mitigate the consequences of the event and bring the unit to a stable condition are recorded.

Salem Unit 1/2 4 Rev. 0

AD-3.1.10 Any equipment out of service which would prevent the unit from being returned to service has been recorded.

3.1.11 All Technical Specification or Adminstrat~ve Action Statements that are required to be cancelled prior to reactor startup have been recorded. (Administrative Action Statements as identified in other Operations Department Directives, such as defined in OD-12.)

3.1.12 Any corrective actions that are required prior to the unit's return* to service are recorded.

3.1.13 The names and assigned positions of all individuals involved in the event are recorded.

3.2 The Senior Shift Supervisor shall sign and date the report.

3.3 The Operations Manager shall be 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~

I 4.0 APPROVAL REQUIREMENTS FOR REACTOR STARTUP 4.1 Startup Approval After Controlled Shutdowns.

4.1.1 The approval for reactor startup after planned unit outages for maintenance/refueling activities shall be obtained from the Operations

  • Manager-Salem Operations. I'f the Operations Manager is not available then the individuals who are authorized to assume the Operations.Manager's responsibilities may authorize the reactor startup.

4.2 *startup Approval After Reactor Trips/Safety Injection Events.

4.2.1 Prior to requesting approval to startup the reactor after any Reactor Trip or Safety Injection, the Post Trip Review must be completed and evaluated.

I Salem Unit 1/2 5: Rev. O

  • I

4.2.2 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.

  • 4.2.3 . If the Operations Manager-Salem Operations is not available then the individuals who are authorized to assume the Operations Manager's

~esponsibilities may authorize the reactor startup.

4.2.4 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 Cormnittee. Upon completion of the evaluation of the event by the Station Operations Review Cormnittee, the Committee shall make recommendations to the General Manager-Salem Operations on reactor startup. Upon completion of the review and satisfactory determination that the unit can be restarted safely, the General Manager-Salem Operations may authorize the reactor startup.

END OF PROCEDURE FINAL PAGE Salem Unit 1/2 6 Rev. 0

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  %

Personnel Assignments SS SSS

~

Board NCO Desk NCO Prim a r y EO Secondary EO Shift Technician SS up S _________________________

Shift Electrician 0ther -----------

(Relay Dept., I&C, Maint., Maplewood Lab etc.)

What evolutions were in progress at the onset of the event:

Surveillance Testing Yes Trouble Shooting or Maintenance Yes No

--- No Unit Startup or Shutdown Activities Yes No Other Activities which could have contributed to the event ---

\

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 Centro 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-l Re"r. 0

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DESCRIPTION OF THE EVENT Reactor Trip Initiation Automatic Yes No If no, explain why. ------

Safety Injection Initiated Yes If initiated, was it automatic ....-----Yes No No If no, explain why.

Does the Sequence of Events Printout from the P-250 agree with the 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) i\

Do the recorder charts indicate any trends which may have contributed to the event?

Yes No --,,.--...,...

If yes, explain in detail.

Were there any alarms which annunciated which were unusual for the event?

Yes No

--=----

If yes, explain in detail.

Were there any ala:ans which should nave annuciated.but did not?

Yes No If yes, explain in detail.

Salem Unit 1/2 AD-16-A-2 Rev. 0

    • Explain in detail the sequence of events which led to the initiation of the event and the actions performed to place in a stable condition. Include the observations and actions of

.specific individuals. Attach additional pages as required

  • i

\,

Salem Unit 1/2 AD-16-A-3 Rev. 0

\

CORRECTIVE ACTIONS Is there any equipment out of ser*v*ice which would prevent the unit from being returned to service? \

Yes No If yes, explain *in_,,,,d_e_t_a..,....il. . \

Are there*any Technical Specification or Administrative Action Statements in effect which would prevent the unit from returning to service? (Administrative Action Statements are described in OD-12 or other Operations Department 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 recommendations as appropriate.

Report Prepared By Date Time Report Reviewed With Date Time Approval to startup granted by Date Time Senior .Shift Supervisor Review_ __..-- --

Date Time

. (Signature) '

Salem Unit 1/2 ' AD-16-A-4 RP-V. 0

Corrective actions required to prevent reoccurrence of this event.

Report Reviewed By Operations Manager Date~~~~~~~

Time ~~~~

  • (signature)

NOTE: This review is not required prior to authorizing startup.

  • Salem Unit 1/2 AD-16-A-5 Rev. 0

I*

~nticipated Transient

~ithout Trip Event (Salem Nuclear Station February 25, 1983)

Lecture Date:

Exam Date:

All work done on this examination is my own, I have neither given nor received aid.

(Signature)

SAOP8302:3

1. Significant events are defined in 10CFRS0.72 as follows:
1) Any event requiring initiation of the licensee's emergency plan or any section of that plan.
2) The exceeding of any Technical Specification Safety Limit.
3) Any event that results in the nuclear power plant not being in a controlled or expected condition while operating or shut-down.
4) Any act that threatens the safety of the nuclear power plant or site personnel, or the security of special nuclear material, including instances of sabotage or attempted sabotage.
5) Any event requiring initiation of shutdown of the nuclear power plant in accordance with Technical Specification Limiting Conditions for Operation.
6) Personnel error or procedural inadequacy which, during normal operations, anticipated operational occurrences, or accident conditions, prevents or could prevent, by itself, the fulfillment of the safety function of those structures, systems, and componenets important to safety that are needed to (i) shut-down the reactor safely and maintain it in a safe shutdown condition, or (ii) remove residual heat following reactor shutdown, or (iii) limit the release of radioactive material to acceptable levels or reduce the potential for such release.
7) Any event resulting in manual or automatic actuation of Engineered Safety Features, including the Reactor Protection System.
8) Any additional, unplanned, or uncontrolled radioactive release (Normal or expected releases from maintenance or other operational activities are not included).
9) Any fatality or serious injury occurring on the site and requiring transport to a~ offsite medical facility for treatment.
10) Any serious personnel radioactive contamination requiring extensive onsite decontamination or outside assistance.

SAOP8302:3

11). Any event meeting the criteria of 10 CFR 20.403 for notification.

12) Strikes of operating employees or security gaurds, or honoring of picket lines by these employees.

(b) With respect to the events reported under paragraphs (a) (1), (2), (3) and (4) of this section, each licensee, in addition to prompt telephone*

notification, shall also establish and maintain an open, continuous communication channel with the NRC Operations Center, and shall close this channel only when notified by NRC.

Item number (l, 2, 3 *** 12) identifies the event we recently had at Salem Unit l on February 25, 1983.

2. In accordance wi~h our Emergency Plan this event of February 25, 1983 wa~ classified as an
3. This event required notification to the NRC Operations Center, located in Bethesda, Md. as*soon as possible and in all cases within by telephone.

(time)

I I

I I

I I

I

4. In accordance with EI-4.3, Reactor Trip, if an automatic reactor trip has ~ occurred the operator is to perform i steps until the reactor is successfully tripped. List these 7 steps.

-I

s. AS a result of this event, February 25, 1983; change in the operation of our manual reactor triE. switch (handle).

will soon be incorporated into EI-4.3, Reactor Trip (Emergency Instruction)

  • Discuss this change!
6. Upon review of the Post-Trip Analysis as shown below (duplicating an actual printout). Explain items (a) and (b} *
  • su or: FnW.11 -At oolz.1*311 00001
  • LD4~~ti*l i-:....---MH Rtl\eteR "'tPST" ;EM LO LO L 4 F"T T"F SET OJ27** L044bD*l lt'1 ceN LO LO L 11.EAttORrRl TRFruF sn JR1' au T"F SE-1.

1 ~~-..gg.;;....c-~N-Ul-Ol...--aou--liltAO-~lil-liJ;ltOR*~~~------,__.

__.JeiOC 100040*0 9'EAClO~ "4'NUAL 1"JF l MT UF l84\* Y400JO*l fURBINE fPlF TRJF 1

a' Ll-__,.__a..A4~~ GGb9

  • 9 RC: M 1 CIR "Al M~ p-(ltc:tr-A--l--lUllR~l~F-~-

182 vonoro~o REACJOR "AlN JRlF B~R 8 tRIF 18471 Yi005D*l 1UF81HE "~HOTE EHEFG T"lF T"lF u---'l-8HC :ygjilQ*l UJdlMii ;roF YA ll-f:\:OSEG-*----

~18481 Y~004D*l "fAC109' nAHUAl T"IF l T9'1F

  • lB'1' N0013D*~ FH~ ~HG 3 FlD FRf F~H RESET b) _1---~*~0t;. 'ttilnD*t lUS:UM5 J.lQF'.-;\IA- .a~-CL..Oi5utJ-----

1850* HOOliO~O FUR ~HG 7 FlU FRf F~H RE3Ef 1~51* HOOllO~O f~" RNG l FlO F"T F"H "ES~l

.llSlC NQO&*o*a ~~~RMC LO--G-%-f~F-1~~-~;*;.f-..~--

SAOP8302:3

Anticipated Transient Without Trip Event (Salem Nuclear Station February 25, 1983)

,'J Lecture Date:

Exam Date:

All work done on this examination is my own, I have neither given nor received aid.

(S igna tu re)

a. During the transient on Febraury 25, 1982 the overhead alarm F-10 ns-G Lo Lo Lvl R.T.n was received. What is th~ logic and setpoint associated with a reactor trip due to S-G Lo-Lo level?
b. Initia1.ly into the transient overhead alarm F-46 "Reactor Trip Turbine Trip" was not received. What conditions must be necessary to actuate this alarm?
a. In accordance with the emergency plan this transient was classified as an
b. In accordance with 10CFR50.72 this event was classified as a significant event. For a significant everit the NRC must be contacted within (time)
3. a. The solid state protection system causes a reactor trip by:

l) energizing the under voltage coil

2) energizing the shunt trip device
3) deenergizing the shunt trip device
4) deenergizing the under voltage coil*
b. Explain what occurs, if anything, to the under voltage coil and the shunt trip device associated with the reactor trip breakers when the manual trip switch on the control board is placed in the trip position.

i *

      • In accordance with EI-4.3, Reactor Trip, if an automatic reactor trip has not occurred the operator is to perform 7 steps until the reactor is successfully tripped. List these 7 steps .

/

5. Discuss the procedure change associated with EI-4.3, in reference to the use of the manual reactor trip switch
  • Appendix B Maintenance Department Procedures M3Q-2, Reactor Trip and Bypass ACB Semi-Annual Inspection and Testing M32, Electrical Equipment Trouble Shooting and Repair
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