ML18096A143

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Rev 12 to Salem Generating Station Event Classification Guide.
ML18096A143
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/28/1991
From: Fawcett D
Public Service Enterprise Group
To:
References
PROC-910628, NUDOCS 9107220063
Download: ML18096A143 (13)
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PUBL ERVICE ~LECTRIC & GAS COM _ Y DOCUMENT DISTRIBUTION NOTICE PAGE 1 OF 1 TRANSMITTAL: DDG 0193585 TO: NUCLEAR REGULATORY COMMISSION 111111111111111111111111111111111111111111111 DOCUMENT CONTROL DESK COPYHOLDER: SECGOlOl WASHINGTON, DC 20555 DESCRIPTION: LJC-SECG PLEASE INSERT THE FOLLOWING DOCUMENTS INTO YOUR CONTROLLED FILE/MANUAL.

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SALEM GENERATING STATION EVENT CLASSIFICATION GUIDE June 28, 1991 CHANGE PAGES FOR REVISION #12 The Table of Contents forms a general guide to the current revision of each section of the SALEM ECG. The changes that are made in this TOC Revision #12 are shown below. Please check that your revision packet is complete and remove the outdated material listed below.

ADD REMOVE

/

Page/ Description Rev. Page Description Rev.

~2 27, TOC 12 1 of 2 TOC 11 thru 2 of 2 1 2 Sec .. Sig. Page 8 1 of 2 Sec. Sig. Page 7 2;<

t 1

u 1 sec iii 5 thru 2 of 2 1 of 1 Sec iii 4

  • At) Section 18 4 All Section 18 3
  • Salem-ECG 1 of 1
- .. . \2>>!:* \'d. ~

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  • ) . ~ 'J-. ~?-~\i I

- ... 'J--r1 ~-l9, ~

SALEM EVENT CLASSIFICATION TABLE OF CONTENTS May 30, 1991 of 2 SE CTI t,O ~

~\ n ';}.'J--Oow

  • TITLE PAGES EFFECTIVE DATES T.O.C. C\\ D Table of Contents 11 2 May 30' 1991 Sig. Identif ication/Signatur 7 2 May 30, 1991 Sig. Att. Attachments/Signature 9 2 Apr 26, 1991
i. 0 4 May 26, 1989 ii. o Requirement 1 10 May* 30, 1991 iii. Cross Events 4 1 Nov 2, 1990
1. 2 3 May 30, 1991
2. 0 1 May 26, 1989
3. FAILURE 1 2 Nov 2' 1990 4* LOSS OF 0 2 May 26, 1989
  • 5.

6.

7.

FUEL 1 0

0 2

1 5

Sept 15, 1989 May May 26, 1989 26, 1989

8. OACTIVE LEAK/SPILL 1 2 Sept 15, 1989 gas, oil spill, hazm
9. RICAL POWER FAILURE 1 2 Mar 2, 1990
10. OF INTRUMENTS/ALARMS/CO I CATIONS 2 2 Apr 26, 1991
11. ROOM EVACUATION 0 1 May 26, 1989
12. (earthquake, 0 6 May 26, 1989
13. SITE HAZARDS 0 5 May 26, 1989 (aircraft crash, etc.)
14. FIRE 0 1 May 26, 1989
15. PERSONNEL EMERGENCIES/MEDICAL 0 2 May 26, 1989
16. SECURITY EVENTS/FFD 3 July 27, 1990
  • SGS PUBLIC INTEREST ITEMS TECH SPECS/PLANT STATUS CHANGES 3 3 May

~ov 30, 1991 2, 1990 Rev. 11

ECG T.O.C Pg. 2 of 2 SALEM EVENT CLASSIFICATION GUIDE TABLE OF CONTENTS - (Continued)

May 30, 1991 EFFECTIVE ATTACHMENT TITLE REV. PAGES DATE

1. Unusual.Event 5 10 Apr 26, 1991
2. Alert 2 8 Apr 26, 1991
3. Site Area Emergency 2 8 Apr 26, 1991
4. General Emergency 2 10 Apr 26, 1991
5. Reserved
6. CMl Log (UE/A/SAE) 7 8 Apr 26, 1991
7. CMl Log (GE) 7 8 Apr 26, 1991
8. CM2 Log ~ 12 Oct 19, 1990 *.
9. Non-Emergency Notifications Reference 6 2 Apr 26, 1991 10 . One Hour Report - NRC/Region 1 5 July 27, .1990
11. One Hour Report - NRC/OPS (Security) 2 5 July 27, 1990
12. One Hour Report - NRC/OPS 2 5 Apr 26, 1991
13. Reserved
14. Four Hour Report - NRC/OPS 3 5 July 27, 1990
15. Four Hour Report - Environmental 2 5 July 27, . 1990
16. Four Hour Report - Spiil/Hazmat 1 6 July 27, 1990
17. Four Hour Report - Fatality/Medical 3 7 July 27, 1990
18. Four Hour Report - Transportation 1 6 July 27, 1990 Accident
19. Twenty Four Hour Report - FFD .0 3 July 27, 1990
20. Twenty Four Hour Report - NRC/OPS 2 5 July 27, 1990
21. Reportable Event - LACT/MOU 0 2 May 2.6, 1989
22. Other/Engineering 1 3 Mar 2, 1990
23. Written Reports/LERS/Others 1 10 Nov 2' 1990 SGS Rev. 11

ECG Sig. i-18 SALEM Pg. 1 of 2 EVENT CLASSIFICATION GUIDE SECTION SIGNATURE PAGE May 30 1 1991 EFFECTIVE SECTION TITLE REV. PAGES DATES

i. . Introduction 0 4 May 26, 1989 ii. Cross Reference - Event to Requirement 1 10 May 30, 1991 iii. Cross Reference - Attachment to Events 4 1 Nov 2, 1990
1. PRIMARY LEAKAGE/SG TUBE LEAKAGE 2 3 May 30, 1991
2. SECONDARY LEAKAGE 0 1 May 26, 1989
3. FAILURE TO TRIP/RPS PROBLEMS 1 2 Nov 2, 1990
4. LOSS OF DECAY HEAT REMOVAL 0 2 May 26, 1989
5. FUEL DAMAGE/DEGRADED CORE 1 2 Sept 15, 1989
6. FISSION PRODUCT BOUNDARY FAILURE 0 1 May 26, 1989 May 26, 1989
7. RADIOLOGICAL RELEASES/OCCURRENCES 0 5
8. NON-RADIOACTIVE LEAK/SPILL 1 2 Sept 15, 1989 (toxic gas, oil spill, hazmat)
9. ELECTRICAD POWER FAILURE 1 2 Mar 2, 1990
10. LOSS OF INTRUMENTS/ALARMS/COMMUNICATIONS 2 2 Apr 26, 1991
11. CONTROL ROOM EVACUATION 0 1 May 26, 1989
12. QUAKE/STORMS (earthquake, wind, floods, 0 6 May 26, 1989 etc)
13. SITE HAZARDS 0 5 May 26, 1989 (aircraft crash, missiles, explosions, etc.)
14. FIRE 0 1 May 26, 1989
15. PERSONNEL EMERGENCIES/MEDICAL 0 2 May 26, 1989
16. SECURITY EVENTS/FFD 3 3 July 27, 1990
17. PUBLIC INTEREST ITEMS 2 3 May 30, 1991
18. TECH SPECS/PLANT STATUS CHANGES 3 6 Nov 2, 1990
  • SGS Rev. 7

ECG SECTIONS i-18 Pg. 2 of 2 SIGNATURE PAGE Prepared By: l). ~(._£.~ s /z.if e:i' (If Editorial Revisions Only, Last Approved Revision) Date Reviewed By: ~~ c-s~ ~ Quaiif ied Reviewer significant §_afety /JZissue~

j'&~/

( ) Yes ( ~no * * ./ d ..

Reviewed By:

  • V, ~¥~

Departmerit.~anager Date Reviewed By =----"'!~~~_,,,_,.__~f2~--+6-

~-"""""""'~------*____

Emergency PyPa£e~ss Manager

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1

  • Reviewed By: ~l I ' \

N I fl_*

~-=---::-::-~~~~~~-::--:--,--___,.~__.~~---.,.~--=-~----~---:-~-

Gener al Manager - Quality Assurance/Safety Review (If Applicable)

Date SORC Review and Station Approvals Mtg. No. Salem Chairman Mtg. No. Hope Creek Chairman

?@D/91 Date Date

-;M*~ ~ c. \Jowk-eneral Mana~r - Salem N/A-General Manager - Hope Creek i'~/Cft Date Date

  • SGS Rev. 7

ECG Sec. i i i Pg. 1 of 1 CROSS REFERENCE.

ATTACHMENTS TO EVENTS SECTION i i i ATTACHMENT EVENT/INITIATING CONDITION 1 lA, lB, lE, 2A, 2B, 5A, 7A, 7B, 7D, 7E, SA, 9A, lOA, 12A, 120, 12G, 12J, 12M, 13A, 130, 13H, 14A, 15A, 16A, 16B, 16C, 17A, lSA (1,2,3,4,5) I lSB, lSC, lSD, lSE 2 lC, lF, lG, lH, 3A, 4A, SB, 5C, 5E, 7C, 7F, SB, 9B, 9E, lOB, llA, 12B, 12E, 12H, 12K, 12N, 13B, 13E, 13F, 13I, 14B, 16D, 16E, 17B 3 lD, lI, lJ, 3B, 4B, 50, 5F, 7G, SC, 9C, 9F, lOC, llB, 12C, 12F, 12I, 12L, 120, 13C, l3G, 13J, 14C, 16F, 17C 4 3C, ~C, 6, 7H, 9D, 12P, 13K, 140, 16G

-* 10 11 12 7I, 7L, 7M 7I, 7K, 16H lK, 7N (2 I 4 I 6) I SD, lOD, 15B, l 7D, lSF I lSG, lSH, lSI, lSJ, lSK 14 3D, 4D, 7N (1,3,5) I 10, 7P, 15C, 17E, lSL, lSM, lSN, lSO 15 17F, 17G 16 SE, SF 17 15D, 15E 18 7J 19 16I 20 lL, lSP, lSQ, lSR, lSS 21 17H 22 18T, lSU, lSV, lSW, lSX

  • SGS Rev. 4

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 18 Pg. 1 of 6 A. UNIT SHUTDOWN INITIATED TO COMPLY WITH THE FOLLOWING TECH. SPEC. LCO'S:

INITIATING 1. REACTOR COOLANT 2. SPECIFIC ACTIVITY OF 3. A.C. ELECTRICAL 4. REACTOR COOLANT 5. PRIMARY CONTAINMENT SYSTEM LEAKAGE THE PRIMARY COOLANT POWER SOURCES SYSTEM PRESSURE/ INTEGRITY CONDITIONS TEMPERATURE LIMITS I IF IF IF IF IF I Unit shutdown is Unit shutdown is Unit shutdown is Unit shutdown is Unit shutdown is initiated as o result i nitioted o s a resu It initiated as a result initiated as o result initiated as o result I of exceeding any of of exceeding any of of exceeding any of of exceeding any of the following T/S of, exceeding any of the following T/S the following T/S the following T/S the following T/S I Action Statements: Action Statements: Action Statements: Action Statements: Action Statements:

I T/S LCO 3.4.6.2 ~U/1 T/S LCO 3.4.7.2 U/2 l T/S LCO 3.4.8 ~U/ll T/S LCO 3.4.9 U/2 T/S LCO 3.8.1.1 T/S LCO .3.4.9 (U/1)

T/S LCO .3.4.10 (U/2)

T/S LCO .3.6. 1.1 I

THEN THEN THEN THEN THEN I

EALS I

I I

I tiQIE.; tiQIE.; liQ1E.: liQ1E.:

,___ _ Refer to ECG SECTION 1 _ _ Refer to ECG SECTION 5 ~ _ Refer to ECG SECTION 9 _ _ Refer to ECG SECTION 6 _

I prior to classification for prior to classification for prior to classificotion for possible escalating prior to classification for possible escalating possible escalating possible escalating I conditions. conditions. conditions. conditions.

NOTE:

Refer to EAL 1BR I - - for Containment Degradation found I during shutdown.

I I

L REFER TO NOTIFICATION/ ATTACHMENT 1 REPORTING UNUSUAL EVENT SGS REV. 3

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTl8N 18 Pg. 2 of 6 B. EXCEEDING ANY T/S SAFETY C. MANUAL OR AUTOMATIC D. LIQ!llil RELEASE THAT EXCEEDS E. GASEOUS RELEASE THAT EXCEEDS F. THE INITIATION OF ANY UMIT ECCS ACTUATION lIITll T/S LIMITS FOR ~ 15 MINS. T/S UMITS FOR ~ 15 MINS. PLANT SHUTDOWN INITIATING DISCHARGE TO THE VESSEL REQUIRED BY THE CONDITIONS TECHNICAL SPECIFICATIONS.

(10CFR50.72 (b}(l)(i)(A)]

I IF IF IF IF IF I Exceeding any T/S 1. ECCS octuation indicated: Valid RMS ALARM on Wl)l Valid RMS 'indication of Unit shutdown is initiated Safety Limit: of the following: either of the following: to comply with Technical I a) ECCS trip setpoint reached or monual R13 Total plant release rate Specifications other R18 (summation of Unit 1 than those specifically listed I T/S 2.1.1 initiation:

OR R19 or and Unit 2) that is: in EAL 18A or 188 OR I T/S 2.1.2 b) Lit logic lights for ony single or 2R37 ~ 2.37E+5 µCi/sec NG (per AOP-RAD-3)

THEN coincidence initiation OR THEN RP4 AND

~ 2.1 E+1 µCi/sec 1-131 Confirmed analysis of (per vent sample)

EALS AND Liquid waste effluent exceeding T/S limits.

2. Discharge to vessel is verified by control AND AND console indication (flow, valve positions, Release has losted or Release has lasted or tank levels, etc.) is expected to last for is expected to last for

~ 15 mins. ~ 15 mins.

THEN THEN THEN tilllE: tilllE: tilllE:

Refer to ECG SEC TION 3 Refer to ECG SEC TION 1 Refer to ECG SECTION 7

- - prior to classifica tion for - - prior to classifica tion for ~ - prior to classification for possible escalatin g possible escalatin g possible escalating conditions conditions conditions.

L_

NOTIFICATION/ REFER TO REFER TO REFER TO REFER TO ATTACHMENT 1 ATTACHMENT 1 ATTACHMENT 1 ATTACHMENT 12 REPORTING UNUSUAL EVENT UNUSUAL EVENT UNUSUAL EVENT ONE HOUR REPORT SGS REV. 3

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 18 Pg. 3 of 6 G. ANY DEVIATION FROM T/S H. ANY EVENT OR CONDITION I. MAJOR LOSS OF EMERGENCY J. ANY THROUGH WALL LEAKS K. ANY UNPLANNED OR OR LICENSE CONDmON IN AN DURING OPERATION THAT ASSESSMENT CAPABIUTY, IN CODE CLASS 1, 2, OR 3 ACCIDENTAL CRITICALITY INITIATING EMERGENCY lfHEN NEEDED RESULTS IN THE OFFSITE RESPONSE PIPING. [10CFR70.52 (a))

TO PROTECT THE HEALTH CONDITION OF THE PLANT CAPABILITY, OR [10CFR50.72 (b)(l)(ii)(B)]

CONDITIONS AND SAFETY OF THE PUBLIC BEING SERIOUSLY DEGRADED COMMUNICATIONS CAPABIUTY

[10CFR50.72 (b)(l)(i)(B)). [10CFR50.72 (b)(l)(ii)) [10CFR50.72 (b)(l)(v))

I IF IF IF IF IF I Action required because no As judged by the SNSS/EDO, SNSS/EDO judges that o Any through wall leaks Any unplanned or accidental action consistent with T/S on event or condition is major loss of ~ of the ore identified in code criticality I or license con provide found during plant operation following hos occurred: class 1, 2, or 3 piping.

adequate or equivalent that results in the plant, THEN I protection in on emergency including principle safety barriers, being in llll)'. of the (excluding scheduled maintenance or as port THEN I ~ Such action must be approved at least by following conditions: of o preplanned test)

System (ENS).

  • Emergency Telephone THEN I OR System.

EALS In o condition outside the

I design basis

  • Emergency Response Facilities.

OR I In o condition not covered

  • SPDS for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

( ~ 2 CFST's !NOP) t:l.QlE.;

I by operating or emergency procedures

  • All Meteorological data for

> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

For code class 1 piping, RCS Pressure Boundary, refer to EAL 18.A.1 I THEN

  • Other Control Room indications or plant ...... - - prior to classification.

I monitors necessary for occident assessment.

For piping that is part of Pri. Cont. Integrity.

refer to EAL 18.A.5 I prior to classification.

THEN I

I I

I L

NOTIFICATION/ REFER TO REFER TO ATIACHMENT 12 ATTACHMENT 12 REPORTING ONE HOUR REPORT ONE HOUR REPORT SGS REV. 3

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTlON 18 Pg. 4 of 6 L. ACTUATION OF ENGINEERED M. REACTOR TRIP EXCEPT N. ANY EVENT FOUND WHILE 0. EVENT/CONDITION THAT SAFETY FEATURE EXCEPT PREPLANNED SHUTDOWN THAT WOULD HAVE ALONE COULD .HAVE PREPLANNED [10CFR50.72 (b)(2)(ii)] SERIOUSLY DEGRADED PLANT PREVENTED CERTAIN INITIATING (10CFR50.72 (b)(2)(i)] SAFETY FUNCTIONS (10CFR50.72 (b)(2)(ii)]

CONDITIONS [10CFR50.72 (b)(2)(iii)]

IF IF IF IF Any event *or condition that Manual or automatic Reactor Any event. found while the Any event or condition that results in manual or Trip except port of a reactor is shut down, that, !lil2n.e could hove prevented automatic actuation of any preplanned sequence during hod it been found during the fulfillment of the safety Engineered Safety Feature testing or operation. operation, whould hove function of structures or (ESF) including the Reactor resulted in the Plant, systems that ore needed to:

Protection System (RPS). including its principle safety THEN barriers. Shutdown the reactor and maintain it in a safe THEN being seriously degraded shutdown condition OR OR being in on unanalyzed Remove residual heat condition that significantly OR compromises Plant safety.

NOTE:.

Control the release of radioactive material Actuation of an ESF THEN or RPS that is part OR EALS of a preplanned Mitigate the consequences sequence during or on occident.

testing or operation may not be reportable.

Refer to THEN NA-AP.ZZ-0006(0) NOTE:

for clarification. Events covered above may include one or more:

procedural errors, equipment

- - failures AND/OR discovery of design, analysis, fabrication, construction and/or procedural inodequecies.

liOIE:

For ECCS actuation with discharge

-- to the RPV, refer to EAL 18C prior to classification.

L. I NOTIFICATION/ REFER TO ATIACHMENT 14 I REFER TO ATTACHMENT 14 I

REPORTING I FOUR HOUR REPORT I FOUR HOUR REPORT SGS REV. 3

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 18 Pg. 5 of 6 P. VIOLATION OF THE Q. STEAM GENERATOR TUBE R. BOTH FIRE SUPPRESSION S. ABNORMAL DEGRADATION OF INITIATING REQUIREMENTS CONTAINED INSPECTIONS lJHICH FALL WATER SYSTEMS INOPERABLE THE CONTAINMENT STRUCTURE CONDITIONS IN OPERATING LICENSE INTO CATEGORY C-3 [T/S 3.7.10.1] DETECTED WHILE SHUTDOWN

[LICENSE CONDmON 21] [T/S U.5.5c.] *u1 [T/S 4.6.1.6.2]

[T/S 4.4.6.5c.] U2 IF IF IF IF Violation of the requirements Results of SG tube inspections Both fire suppression water Any abnormal degradation of contained in Section 2.C of which fall into Category C-3 systems are inoperable at any the Containment structure is the Operating License

  • of T/S 4.4.5.2(6.2); * . time detected by visual inspection except those provisions of exposed, accessible interior of Section 2.C ,(2) more than 10% of total tubes and exterior surfaces during inspected are degraded tubes THEN shutdown THEN OR more than 1% of the inspected tubes are defective THEN THEN EALS L__

NOTIFICATION/ REFER TO ATTACHMENT 20 REPORTING 24 HOUR REPORT SGS REV. 3

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 18 Pg. 6 of 6 T. EXCESSIVE HEAT UP /COOL U. EVENT RESULTING IN V. EVENT RESULTING IN 'If. RCS CHEMISTRY DETERMINED

  • X. DISCOVERY OF INOPERABLE INITIATING DOWN RATES . DISCHARGE FROM A OVERPRESSURIZATION THAT TO BE OUTSIDE ALLOWABLE SNUBBERS CONDITIONS [T/S 3.U.1 OR 9.2] Ul SAFETY VALVE MAY HAVE AFFECTED THE LIMITS [T/S 3.7.9]

[T/S 3.4.10.1 OR 10.2] U2 [JAN 1983, LTR TO NRC] STRUCTURAL INTEGRITY OF [T/S 3.4.7] Ul THE STEAM GENERATORS [T/S 3.4.8] U2 I [T/S 3.7.2.1] Ul

[T/S 3.7.2] U2 I

IF IF IF IF IF I Any PZR code safety valve The temperature of either The concentration of either One or more snubbers ore Any of the T/S LCO's I for RCS or PZR heatup or co*oldown rates are discharges which requires a necessary inspection of the primary or secondary coolant in any Steam chloride or fluoride in the RCS is in excess of its found to be inoperable and have been replaced or I exceeded. the inlet piping and an engineering evaluation.

Generator is

~ 70 "F when Steady State Limit* for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restored to an OPERABLE stotus, an engineering OR evaluation shall be performed I THEN the pressure of either coolant in the Steam in excess of its Transient per T.S 4.7.9c.

THEN Limit, I Generator is thereby requiring an engineering evaluation to THEN

> 200 psig I determine the effects of the out of limit condition I THEN on the structural integrity of the RCS EALS I THEN I

I I

I I llill.E:

Attachment 22 is for the purpose of initiating I any Tech. Spec. required engineering evaluations.

This Attachment should be implemented in parallel with any other Attachment for non-emergencies I or Unusual Events as needed for Regulatory required Notifications.

I L

REFER TO NOTIFICATION/ ATTACHMENT 22 REPORTING OTHER SGS REV. 3.

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