ML18095A606

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Rev 8 to Event Classification Guide
ML18095A606
Person / Time
Site: Salem  PSEG icon.png
Issue date: 11/01/1990
From: Fawcett D
Public Service Enterprise Group
To:
References
PROC-901101, NUDOCS 9011280180
Download: ML18095A606 (29)
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Text

""-- . . PU~ SERVICE ELECTRIC & GAS ~PANY l~/b9f90 ~ ""'156cuMENT DISTRIBUTION NOTI~ PAGE 1 OF 1 TRANSMITTAL: DDG 0158167 TO: NUCLEAR REGULATORY COMMISSION Illllll lllll 111111111111111111111111111111111 DOCUMENT CONTROL DESK COPYHOLDER: SECGOlOl WASHINGTON, DC 20555 DESCRIPTION: PCR SECG REV 8 PLEASE INSERT THE FOLLOWING DOCUMENTS INTO YOUR CONTROLLED FILE/MANUAL.

SUPERCEDED DOCUMENTS MUST BE SO MARKED AND PHYSICALLY REMOVED OR DESTROYED.

SHT/

CLASS DOCUMENT ID VOL INST REV STAT TYPE FORMAT QTY PROC SECG-TOC 000 008 A SECG H 001

,- - --*~!YI f2i:::i) 1 :::-cT *~1 cS11 (Y1 \

PDR ADOCK 05000272 f/OLfS F PDC PLEASE SIGN AND DATE THIS NOTICE TO ACKNOWLEDGE RECEIPT AND RETURN WITHIN 5 WORKING DAYS TO:

'/ /

DOCUMENT DISTRI~UTION GROUP NDAB, N04 COPYHOLDER SIGNATURE: DATE:

DDG USE ONLY: DATA ENTRY COMPLETED:

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  • SALEM GENERATING STATION EVENT CLASSIFICATION GUIDE e
  • November 2, 1990 CHANGE PAGES FOR REVISION #8 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 #8 are shown below. Please check that your revision packet is complete and remove the outdated material listed below.

ADD REMOVE Page DescriQtion Rev. Page DescriQtion Rev.

1 of 2 TOC 8 1 of 2 TOC 7 thru thru 2 of 2 2 of 2 1 of 2 Sec. Sig. 5 1 of 2 Sec. Sig. 4 thru thru 2 of 2 2 of 2 1 of 2 Sig. Att. 7 1 of 2 Sig. Att. 6 thru thru 2 of 2 2 of 2 1 of 1 Sec iii 4 1 of 1 Sec iii 3 thru thru 1 of 1 1 of 1 1 of 2 Section 3 1 1 of 2 Section 3 0 thru thru 2 of 2 2 of 2 1 of 2 Section 10 1 1 of 2 Section 10 0 thru thru 2 of 2 2 of 2 1 of 6 Section 18 3 1 of 6 Section 18 2 thru thru 6 of 6 6 of 6 1 of .10 Att. 23 1 1 of 10 Att. 23 0 thru thru 10 of 10 10 of 10

    • Salem-ECG 1 of 1

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~ITLE SALEM EVENT CLASSIFICATION GUIDE TABLE OF CONTENTS OCTOBER 19 1 1990 PAGES Pg. 1 of 2 EFFECTIVE DATES T.O~C. ~Table of Contents 7 2 Oct 19, 1990 Sig. i..;18 S,ection Identification/Signature Page 4 2 July 27, 1990 Sig. Att. E~~ Attachments/Signature Page 6 2 Oct 19, 1990

\ .

i. Int:r;oduction 0 4 May 26, 1989 ii. Cross *.,Reference - Event to Requirement 0 10 May 26, 1989

}:\

iii. Cross R~f) erence - Attachment to Events 3 1 July 27, 1990

\

1. PRIMARY LEAKAGE/SG TUBE LEAKAGE 1 3 Sept 15, 1989

\

2. SECONDARY LEAKAGE 0 1 May 26, 1989
3. FAILURE TO TRIP,/RPS PROBLEMS 0 2 May 26, 1989
4. LOSS OF DECAY HEAT REMOVAL 0 2 May 26, 1989

\\

5. FUEL DAMAGE/DEGRADEp CORE 1 2 Sept 15, 1989
  • \
  • )

, 6. FISSION PRODUCT BOUNBARY FAILURE 0 1 May 26, 1989

7. RADIOLOGICAL

\

RELEASES/O~CURRENCES 0 5 May 26, 1989

8. .

NON-RADIOACTIVE "'

LEAK/SPILL, 1 2 Sept 15, 1989 (toxic gas, oil spill, hazmq,t)

\

9. ELECTRICAL POWER FAILURE 1 2 Mar 2' 1990
10. LOSS OF INTRUMENTS/ALARMS/COMMUNICATIONS 0 2 May 26, 1989
11. CONTROL ROOM EVACUATION ~ 0 1 May 26, 1989
12. QUAKE/STORMS (earthquake, wind, . fl\oods, 0 6 May 26, 1989 etc) '\

\

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13. SITE HAZARDS . \

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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 Ju.ly 27, 1990
17. PUBLIC INTEREST ITEMS 1 Sept 29, 1989
18. TECH SPECS/PLANT STATUS CHANGES 2 '1, 1990

\.

SGS

.~

~

' ' . ECG T.O.C Pg . 2 of 2 SALEM EVENT CLASSIFICATION GUIDE TABLE OF CONTENTS - (Continued)

OCTOBER 19 1 1990 EFFECTIVE ATTACHMENT TITLE REV. PAGES DATE

1. Unusual Event 4 10 July 27, 1990
2. Alert 1 8 Mar 2, 1990
3. Site Area Emergency 1 8 Mar 2, 1990
4. General Emergency 1 10 Mar 2I 1990
5. Reserved
6. CMl Log (UE/A/SAE) 5 6 Oct 19, 1990
7. CMl Log (GE) 5 7 Oct 19, 1990
8. CM2 Log 4 12 Oct 19, 1990
9. Non-Emei;gency Notifications Reference 5 2 Oct 19, 1990 One Hour Report - NRC/Region 1 5 July 27, 1990

.10.

11. one Hour Report - NRC/OPS (Security) 2 5 July 27, 1990 12 .. One Hour Report - NRC/OPS 1 5 July 27, 1990
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 - Spill/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 26, 1989
22. Other/Engineering 1 3 Mar 2I 1990

.23. Written Reports/LERS/Others 0 10 May 26, 1989

\i SGS Rev. 71

ECG s*ig. i-18

    • SALEM EVENT CLASSIFICATION GUIDE SECTION SIGNATURE PAGE July 27, 1990 Pg. 1 of 2 "EFFECTIVE SECTION TITLE REV. PAGES DATES
i. Introduction 0 4 May 26, 1989 ii. Cross Reference - Event to Requirement 0 10 May 26, 1989 iii. Cross Reference - Attachment to Events 3 1 July 27, 1990
1. PRIMARY LEAKAGE/SG TUBE LEAKAGE 1 3 Sept 15, 1989
2. SECONDARY LEAKAGE 0 1 May 26, 1989
3. FAILURE TO TRIP/RPS PROBLEMS 0 2 May 26, 1989
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
7. RADIOLOGICAL RELEASES/OCCURRENCES 0 5 May 26, 1989 NON-RADIOACTIVE LEAK/SPILL 1 2 Sept 15, 1989 (toxic gas, oil spill, hazmat)
9. ELECTRICAL POWER FAILURE 1 2 Mar 2, 1990
10. LOSS OF INTRUMENTS/ALARMS/COMMUNICATIONS 0 2 May 26, 1989
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 1 3 Sept 29, 1989
18. TECH SPECS/PLANT STATUS CHANGES 2 6 Mar 2, 1990
  • SGS Rev. ~

ECG

    • SIGNATURE PAGE SECTIONS i-18 Pg. 2 of 2 Prepared By: ]), ~v-1az..-rr- ?h/.t:t; (If Editorial Revisions Only, Last Approved Revision) Date Reviewed By=~~~~~----=~~~=-z.=-::.==::=;:::::;:::::::.i..-~~~~~~~~~~~

Sta~~lified Reviewer* ~

,/~dtJ'l Signific~n_). Safety Issue

( ) Yes PS-!_ no Reviewed By:~~~~~~~~~._.._~.....,,...~~~~~~~~~~~~ ")-10-~0 Depaltmen't> Manager Date z..;.10.,.fu

'Date

/A Reviewed By:  ;.J General Manager - Quality Assurance/Safety Review Date (If Applicable)

SORC Review and Station Approvals Mtg. No. Salem Chairman Mtg. No. flope Creek Chairman

~

'Date Date General Manager - Salem~ General Manager - Hope Creek Date

  • SGS Rev. 4 '*

ECG

' . SALEM Sig. Att.

Pg. 1 of 2 EVENT CLASSIFICATION GU~DE

      • ATTACHMENT TITLE ATTACHMENTS SIGNATURE PAGE October 19, 1990 PAGES EFFECTIVE DATE
1. Unusual Event 10 July 27, 1990
2. Alert 1 8 Mar 2, 1990
3. site Area Emergency 1 8 Mar 2, 1990
4. General Emergency 1 10 Mar 2, 1990
5. Reserved
6. CMl Log (UE/A/SAE) 5 6 Oct 19, 1990
7. CMl Log (GE) 5 7 Oct 19, 1990
8. CM2 Log 4 12 Oct 19, 1990
9. Non-Emergency Notifications 5 2' Oct 19, 1990 Reference
10. One Hour Report - NRC/Region 1 5 July 27, 1990
  • 11.

12.

13.

One Hour Report - NRC/OPS (Security)

One Hour Report - NRC/OPS Reserved 2

1 5

5 July 27, 1990 July 27, 1990

14. Four Hour Report - NRC/OPS 3 5 July 27, 1990
15. Four Hour Report - 2 5 July 27, 1990 Environmental
16. Four Hour Report - 1 6 July 27, 1990 Spill Hazmat
17. Four Hour Report - 3 7 July 27, 1990 Fatality/Medical
18. Four Hour Report - 1 6 July 27, 1990 Transportation Accident
19. Twenty Four Hour Report - FFD 0 3 July 27, 1990
20. Twenty Four Hour Report - 2 5 July 27, 1990 NRC/OPS
21. Reportable Event - LACT/MOU 0 2 May 26, 1989
  • 22. Other/Engineering 1 3 Mar 2 / 1990
23. Written Reports/LERS/Other 0 10 May' 26, 1989 SGS Rev. 6

ECG ATT. 1-23 Pg. 2 of 2 SIGNATURE PAGE Prepared By: D. FA..-.;l,.L. rr (If Editorial Revisions Only, Last Approved Revision)

/ZJ :-r lo >'iJ Date Reviewed By:

station Qualified _Reviewer Date Significant Safety Issue

( ) Yes ( ) no Reviewed By:

Department Manager Date Reviewed By: Iv-?-? J Emergency Preparedness Manager Date Reviewed By: J... ( /l General Manager - Quality Assurance/Safety Review Date (If Applicable)

SORC Review and Station Approvals Mtg. No. Salem Chairman Mtg. No. 'Hope Creek Chairman Date Date J-/1 p ~1,4-General Manager - Salem General Manager - Hope Creek Date Date

    • SGS Rev. 6

..1

__J

~

ECG

    • CROSS REFERENCE Sec. i i i Pg. 1 of 1 ATTACHMENTS TO EVENTS SECTION i i i ATTACHMENT EVENT/INITIATING CONDITION 1 1A, 1B, 1E, 2A, 2B, SA, 7A, 7B, 7D, 7E, BA, 9A, 10A, 12A, 120, 12G, 12J, 12M, 13A, 130, 13H, 14A, 1SA, 16A, 16B, 16C, 17A, 18A (1,2,3,4,S),

18B, 18C, 180, 18E 2 1C, 1F, lG, lH, 3A, 4A, SB, SC, SE, 7C, 7F, BB, 9B, 9E, lOB, 11A, 12B, 12E, 12H, 12K, 12N, 13B, 13E, 13F, 13I, 14B, 16D, 16E, 17B 3 1D, lI, 1J, 3B, 4B, SD, SF, 7G, SC, 9C, 9F, 10C, 11B, 12C, l2F, 12I, 12L, 120, 13C, 13G, 13J, 14C, 16F, 17C 4 3C, 4C, 6, 7H, 90, 12P, 13K, 14D, 16G

  • 10 11 12 7I, 7L, 7M 7I, 7K, 16H 1K, 3D, 7N (2,4,6), SD, 10D, 1SB, 170, 18F, 18G, l8H, 18I, 18J, 18K 14 3E, 4D, 7N (1,3,S), 70, 7P, lSC, 17E, 18L, 18M, 18N, 180 1S 17F, 17G 16 BE, SF 17 lSO, lSE
18. 7J 19 16I I

20 lL, 18P, 18Q, 18R, 18S 21 17H 22 18T, 18U, 18V, 18W, 18X

  • SGS Rev. 3

ECG SECTION 3 FAILURE TO TRIP / RPS PROBLEMS SECTION 3 Pg. 1 of 2 ANTICIPATED TRANSIENT WITHOUT TRIP (ATWT)

A. FAILURE OF THE RPS TO AUTOMATICALLY B. FAILURE OF THE RPS TO AUTOMATICALLY C. TRANSIENT REQUIRING OPERATION OF INITIATE AND COMPLETE A TRIP WHICH OR BY OPERATOR ACTION TO MANUALLY, SHUTDOWN SYSTEMS WITH FAILURE INITIATING BRINGS THE RX SUBCRITICAL INITIATE AND COMPLETE A TRIP TO TRIP, RESULTING IN CORE WHICH BRINGS THE RX SUBCRITICAL DAMAGE OR ADDITIONAL FAILURE OF CONDITIONS CORE COOLING AND MAKEUP SYSTEMS I IF IF IF I Receipt of RX Protection logic input on RP4 Receipt of RX Protection logic input on RP4 Receipt of RX Protection logic input on RP4 I

AND AND AND I

Autqmatic Rx Trip did not Automatic Rx Trip did not Automatic Rx Trip did not I bring the Rx subcritical bring the Rx subcriticol bring the Rx subcriticol I THEN AND AND I Manual Rx Trip did not Manual Rx Trip did not EALS I bring the Rx subcriticol bring the Rx subcriticol I AND AND I RCS Borotion m to bring the RX Subcriticol RCS Borotion foils to bring the RX Subcriticol I

THEN I NOTE: AND AND I ifOManual Rx Trip did bring the Rx tJ.Q flow shown on Pumps oQ1 running Subcritical, an ALERT SI / RH R systems with SI initiated I shall be declared

. until the causes and I *consequences of the ATWT ore evaluated.

THEN THEN I

I I

  • . L NOTIFICATION/ REFER TO AITACHMENT 2 REFER TO ATTACHMENT 3 REFER TO ATTACHMENT 4 REPORTING ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SGS REV. 0

ECG SECTION 3 FAILURE TO TRIP / RPS PROBLEMS SECTION 3 Pg. 2 of 2 REPORTABLE EVENTS D. ANY PROBLEMS WITH THE E. EVENT / CONDITION THAT Al&NE RX TRIP BREAKERS COULD HAVE PREVENTED INITIATING (T.S. 3/4.3.1] CERTAIN SAFETY FUNCTIONS (10CFR 50.72 (b)(2)(iii)]

CONDITIONS I IF IF Any event or condition that I alone could have prevented the As judged by the SNSS / EDO fulfillment of the safety function I any problem with the RX trip breakers of structures or systems that are needed to:

I Shutdown the reactor and maintain it in a safe I THEN shutdown condition THEN I

I NOTE: Events covered above may include one or EALS I more:

procedural errors, equipment failures I AND/OR discovery of design, I analysis, fabrication, construction, and/or I procedural inadequacies I

I I

I I

I I

.... L I I NOTIFICATION/

REPORTING I

REFER TO ATTACHMENT 12 ONE HOUR REPORT I REFER TO ATTACHMENT 14 FOUR HOUR REPORT SGS REV. 0

ECG SECTION 10 LOSS OF INSTRUMENTATION/ ANNUNCIATION/COMMUNICATIONS SECTION 10 Pg. 1 of 2 A. INDICATIONS OR ALARMS ON PROCESS OR EFFLUENT PARAMETERS 8. LOSS OF MOST OR ALL C. LOSS OF MOST OR ALL NOT FUNCTIONAL IN CONTROL ROOM. ANNUNCIATION ANNUNCIATION WITH A INITIATING PLANT TRANSIENT CONDITIONS INITIATED/IN PROGRESS LOSS OF ASSESSMENT OR COMMUNICATION CAPABILITY I IF IF IF IF I Indications or alarms Loss of assessment or communications capability Loss of most or all Overhead Annunciators.

Loss of most or all Overhead Annunciators.

on process or effluent I parameters are not functional in Control including any of the following:

I Room *Meteorological Instrumentation

  • SPDS AND AND (excluding scheduled maintenance) SNSS judgement that SNSS judgement that I AND safe operation of plant hos been hindered.

safe operation of plant has been hindered.

I Extent of lost function requires plant shutdown THEN I

EALS I THEN AND AND Extent of loss requires Assessment or communications I plant shutdown capability has been lost for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I AND THEN THEN I A plant transient is initiated or in progress.

I I THEN I

I I

I L

REFER TO REFER TO REFER TO REFER TO NOTIFICATION/ ATTACHMENT 2 ATTACHMENT 3 ATTACHMENT 1 ATTACHMENT 1 REPORTING UNUSUAL EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY SGS REV. 0

ECG SECTION 10 LOSS OF INSTRUMENTATION/ ANNUNCIATION/COMMUNICATIONS SECTION 10 Pg. 2 of 2 D. MAJOR LOSS OF COMMUNICATIONS INITIATING CAPABILITY

[10CFR50.72 (b)(l)(v)]

CONDITIONS IF I SNSS/EDO judges that a major loss of !J.ll.\'. of I the following has occurred:

I

  • EMERGENCY NOTIFICATION SYSTEM (ENS)

I

  • TELEPHONE SYSTEM I THEN EALS I I

I I

I I

I I

I I

L_

    • . NOTIFICATION/

REPORTING I REFER TO 12 ATTACHMENT I ONE HOUR REPORT SGS REV. 0

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 CONDITIONS SYSTEM LEAKAGE THE PRIMARY COOLANT POWER SOURCES SYSTEM PRESSURE/ INTEGRITY 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 a result initiated as a result initiated as o result initiated as a result initiated as a result I of exceeding any of of exceeding any of of exceeding any of of exceeding any of of exceeding any of the following T/S 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 fU/ll T/S LCO 3.4.7.2 U/2 T/S LCO 3.4.8 fU/1 T/S LCO 3.4.9 U/2 l 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 t!QIE.; t!QIE.; t!QIE.; t!QIE.;

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

I t- -

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

NOTE:

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

I I

L NOTIFICATION/ REFER TO ATTACHMENT 1 I

REPORTING I~

UNUSUAL EVENT SGS REV. 2

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 18 Pg. 2 of 6 B. EXCEEDING ANY T/S SAFETY C. MANUAL OR AUTOMATIC D. WllilJ) RELEASE THAT EXCEEDS E. GASEOUS RELEASE THAT EXCEEDS F. THE INITIATION OF ANY LIMIT ECCS ACTUATION ll'.ITli T/S LIMITS FOR ~ 15 MINS. T/S LIMITS 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 actuation indicated: Valid RMS ALARM on !l1l)' 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 selpoint reached or manual 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 18B OR I T/S 2.1.2 b) L'1t logic lights for any single or 2R37 ~ 2.37E+5 µCi/sec NG (per AOP-RAD-J)

THEN I THEN coincidence initiation RP4 AND OR I Confirmed analysis of

~ 2.1E+1 µCi/sec 1-131 EALS Liquid waste effluent (per vent sample)

I AND exceeding T/S limits.

I 2. Discharge to vessel is AND AND NOTE:

I verified by control console indication For compliance with Tech. Spec. J.0.3, refer (flow, valve positions, Release hos lasted or Release has lasted or I tank levels, etc.) is expected to last for

~ 15 mins.

is expected to last for

~ 15 mins.

to OD-12 prior to classification.

I THEN THEN THEN I

I I l::!.QIT; Refer to ECG SE CTION 3 l::!.QIT; Refer to ECG SEC TION 1 NOTE:

Refer to ECG SECTION 7 I prior to classifica ti on for - - prior to c lassifica ti on for >-- - prior to classification for possible escalalin g possible escalatin g possible escalating conditions. conditions conditions.

I L

NOTIFICATION/ REFER TO ATTACHMENT I REFER TO ATTACHMENT I REFER TO ATTACHMENT 1 REFER TO ATTACHMENT 12 I

REPO~TING UNUSUAL EVENT I UNUSUAL EVENT I I UNUSUAL EVENT I I ONE HOUR REPORT SGS REV. 2

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. (RESERVED FOR FUTURE K. ANY UNPLANNED OR OR LICENSE CONDITION IN AN DURING OPERATION THAT ASSESSMENT CAPABIIJTY, USE) ACCIDENTAL CRITICALITY INITIATING EMERGENCY WHEN NEEDED RESULTS IN THE OFFSITE RESPONSE (10CFR70.52 (a)]

TO PROTECT THE HEALTH CONDITION OF THE PLANT CAPABIIJTY, OR CONDITIONS AND SAFETY OF THE PUBLIC BEING SERIOUSLY DEGRADED COMMUNICATIONS CAPABILITY (10CFR50.72 (b)(l)(i)(B)] [10CFR50.72 (b)(l)(ii)] (10CFR50.72 (b)(l)(v)]

I IF IF IF IF I Action required because no As judged by the SNSS/EDO, SNSS/EDO judges that a Any unplanned or accidental action consistent with T/S on event or condition is major loss of QJll' of the criticality I or license can provide found during plant operation following hos occurred:

adequate or equivalent that results in the plant. THEN I protection in an emergency including principle safety barriers, being in QJll' of the

  • Control Room indication or plant monitors I NOTE: .Such action must be

- - approved at least by following conditions: necessary for accident assessment a licensed SRO. An unanalyzed condition I that significantly compromises plant safety.

OR

  • Emergency Communications THEN I OR (including ENS)

EALS In a condition outside the OR I design basis

  • Offsite sirens I OR In a condition not covered THEN by operating or emergency I procedures I THEN I

I I

I I

I L

NOTIFICATION/ REFER TO ATTACHMENT 12 I REFER TO ATTACHMENT 12 f.lEPORTl_NG I ONE HOUR REPORT ONE HOUR REPORT SGS REV. 2

ECG SECTION 18 TECHNICAL SPECIFICATION / PLANT STATUS CHANGES SECTION 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 INITIATING PREPLANNED [10CFR50.72 (b)(2)(ii)] SERIOUSLY DEGRADED PLANT PREVENTED CERTAIN

[10CFR50.72 (b)(2)(ii)] [10CFR50.72 (b)(2)(i)] SAFETY FUNCTIONS CONDITIONS [10CFR50.72 (b)(2)(iii)]

r 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, Q.[Qm: could hove prevented automatic actuation of any preplanned sequence during had 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 are needed to:

Protection System (RPS). THEN including its principle safety 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.

Control the release of NOTE: radioactive material Actuation of an ESF or RPS that is port THEN 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

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

till.IE:

For ECCS actuation with discharge to the RPV, refer to EAL 1BC prior to classification.

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

.REPORTING I rouR HOUR REPORT I FOUR HOUR REPORT SGS REV. 2

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 WHICH 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 CONDITION 21] [T/S 4.4.5.5c.J Ul [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 103 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 I

REPORTING I 24 HOUR REPORT SGS REV. 2

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 W. RCS CHEMISTRY DETERMINED X. DISCOVERY OF INOPERABLE INITIATING DOlfN RATES DISCHARGE FROM A OVERPRESSURIZATION THAT TO BE OUTSIDE ALLOWABLE SNUBBERS CONDITIONS T/S 3.4.9.1 OR 9.2) Ul SAFETY VALVE MAY HAVE AFFECTED THE IJMITS [T/S 3.7.9]

fT/S 3.4.10.1 OR 10.2] U2 (JAN 1963, LTR TO NRC] STRUCTURAL INTEGRITY OF [T/S 3.4.7) Ul THE STEAM GENERATORS [T/S 3.4.6] U2 I [T/S 3.7.2.1) UI

[T/S 3.7.2) U2 I

IF IF IF IF IF I

Any of the T/S LCO's Any PZR code sofety valve The temperature of either The concentration of either One or more snubbers are I for RCS or PZR heatup or coo/down rates are discharges which requires a necessary inspection of the primary or secondary coolant in ony 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 status, an engineering I THEN* the pressure of either coolant in the Steam OR in excess of its Transient evaluation shall be performed 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 till!£;

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

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

I L

NOTIFICATION/ REFER TO ATIACHMENT 22 I

REPORTING I OTHER SGS REV. 2

ECG ATT 23 Pg. 1 of 1.0

  • ATTACBMENT 23
  • WRXTTEN REPORTS/LERS/OTBER NOTES:

This attachment lists additional off normal events for which the initiation of regulatory required written reports may be needed. Tech. Spec. references, as noted, are not always the same for Salem Unit i and 2. (Unit 2 numbers, if different are parenthesized).

The LER Coordinator will determine the proper reporting re-quirements to be met, the responsible department, and the actual reporting reference (i.e. Tech Specs or 10CFR) using the paraphrased event conditions of this attachment as a guide only.

SPECZAL REPORTS (10 - 15 DAYS)

A.01 IF one or more seismic monitoring instruments are inoperable for > 30 days, THEN prepare a 10 Day report per T.S.3.3.3.3.(Ul only).

A. 02 IF a seismic event > O.Olg is detected the recorded data

  • A.03 shall be retrieved from the seismic monitoring instruments and analyzed, THEN prepare a 10 Day report per T.S.4.3.3.3.2.(Ul only).

IF one or more meteorological monitoring channels inoperable for > 7 days, THEN prepare a 10 Day report per T.S.3.3.3.4.(Ul only).

A. 04 IF the moderator temperature coefficient (MTC) is more positive than allowed, THEN prepare a 10 ~ay report per_

T.S.3.1.1.4a.(3.l.l.3a).

B.01 IF the number.of operable process radiation monitoring instrumentation channels is less than the minimum channels operable requirements, THEN prepare a 14 Day report per T.S.3.3.3.1.

B.02 IF a Safety Limit has been violated, THEN prepare a Safety Limit Violation* Report to be submitted within 14 Days per T.S.6.7.1.d. [see ECG Section 18].

c.01 IF an accident occurs during the transportation of licensed material, THEN prepare a 15 Day report that* includes the results of an investigation pertaining to the accident per 10CFR71.5(a)(l)(v) and 49CFR171.16.

c.02 WHEN an inservice inspection of SG tubes is performed, THEN prepare a 15_ Day report per T.S.4.4.5.5a (4.4.6.Sa) that~

provides the number of tubes plugged in each SG.

SGS Rev. O

ECG ATT 23 Pg. 2 of 10

  • D.01 SPECXAL REPORTS (30 DAYS)

IF any incident in which an attempt has been made, or is believed to have been made, to commit a theft or unlawful diversion of special nuclear material OR to commit an act of radiological sabotage against the plant or transportation system, THEN prepare a 30 Day report per 10CFR73.7l(b).

D.02 IF any exposure of an individual in excess of the following limits:

a) Personnel (no Form NRC-4) ,

WB 1.25 Rem/ quarter Skin 7.50 Rem/ quarter Extremities 18.75 Rem/ quarter b) Personnel (Form NRC-4 completed)

WB 3.0 Rem/ quarter Cumulative Dose s.o (N-18) Rems c) Individuals under 18 years of age

  • 10% of the limits specified in a), above.

THEN prepare a 30 Day report per 10CFR20.101, 10CFR20.104, and 10CFR20.405o D.03 IF any incident which would result in a 10CFR20.103(a) (1) individual receiving, during one calendar quarter, from the inhalation or absorption through the skin, a dose that would be greater than the quantity which would ~e received by the inhalation for 40 Hrs. per week for 13 weeks at uniform concentration of radioactive material in air specified in 10CFR20 Appendix B, Table I, THEN prepare a 30 Day report per 10CFR20.405.

D.04 IF any incident which would result in an individual inhaling or absorbing through the skin a quantity of uranium in excess of the limits specified in 10CFR20 Appendix B, Table I, THEN prepare a 30 Day report per 10CFR20.103(a) (2) and 10CFR20.405.

D.05 WHEN radiation exposure data is reported to an individual i.a.w 10CFR19.13, THEN prepare a 30 Day report pe~

10CFR20.405 and/or 10CFR20.408 *

  • SGS Rev.~. O

ECG ATT 23

    • D.06 IF any incident in which levels of radiation or Pg. 3 of 10 concentrations of radioactive materials, in an unrestricted area exceed 10 times the limits of 10CFR20, THEN prepare a 30 Day report per 10CFR20.405(a) (1) (v).

D.07- IF levels of radiation or releases of radioactive material exceed limits specified in 40CFR190, THEN prepare a 30 Day report per 10CFR20.405(c) (1).

D.08 IF the calculated dose or dose commitment to a MEMBER OF. THE PUBLIC from radioactive materials in Liquid Effluents exceeds:

1.5 mR to the total body or 5.0 mR to any organ during any calendar quarter OR 3.0 mR to the total body or 10 mR to any organ during any calendar year, THEN prepare a 30 Day report per T.S.

3.11.1.2.

D.09 IF the projected dose to Unrestricted Areas when radioactive liquid waste is discharged is in excess of: 0.375 mR to the total body or 1.25 mR to any organ during any 31 day period AND any portion of the Liquid Radwaste Treatment system is not in operation, THEN prepare a 30 Day report per T.S. 3.11.1.3.

D.10 IF the calculated air dose from noble gas released in gaseous effluents exceeds: 5 mrad for gamma or 10 mrad for beta radiation during any calendar quarter OR 10 mrad for gamma or 20 mrad for beta radiation during any calendar year, THEN prepare a 30 Day report per T.S.

3.11.2.2.

D.11 IF the calculated dose from release of I-131, I-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in Gaseous Effluents exceeds:

7.5 mR to any organ during any calendar quarter OR 15 mR to any organ during any calendar year, THEN prepare a 30 Day report per T.S. 3.11.2.3.

D.12 WHEN the projected ga~eous effluent air doses due to releases from the site to areas at or beyond the MEA exceed 0.625 mrad for gamma or 1.25 mrad for beta radiation and those releases are being discharged without treatment, in lieu of an LER, THEN prepare a 30 Day report per T.S.3.11.2.4 *

  • SGS Rev. o~

ECG ATT 23 Pg. 4 of 10 D.13 IF radioactive ventilation exhaust from the Reactor Bldg and Service and Radwaste Bldg is discharged without treatment AND the projected dose beyond the SITE BOUNDARY over any calendar quarter exceeds: 1.875 mR to any organ of a MEMBER OF THE PUBLIC THEN prepare a 30 Day report per T.S.3.11.2.4.

D.14 IF the calculated total annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactive materials and to radiation from uranium fuel cycle sources exceeds:

25 mR to the total body or any organ except thyroid OR 75 mR to the thyroid 1 THEN prepare a 30 Day report per T.S.3.11.4.

D.15 IF the measured radioactivity concentration levels in environmental samples, resulting from plant effluents, exceeds the reporting thresholds of Table 3.12.1-2 when averaged over any calendar quarter, THEN prepare a 30 Day report per T.S.3.12.lb.

D.16 IF either the POPs or the RCS vent(s) are used to mitigate an

  • D.17 RCS pressure transient, THEN prepare a 30 Day report per T.S.3.4.9.3 (3.4.10.3).

IF less than the minimum required fire detection instrumentation for each detection zone is OPERABLE AND the inoperable instrument(s) are not restored to an OPERABLE status within 14 days, THEN prepare a 30 Day report per T.S.3.3.3.6.

D.18 IF one pump and/or one water supply of the two fire suppression water systems becomes inoperable AND the inoperable equipment is not restored to an OPERABLE status within 7 days, THEN prepare a 30 Day report per T.S.3.7.10.1.

D.19 IF one or more of the required spray and/or sprinkler systems becomes inoperable AND the system is not restored to an OPERABLE status within 14 days, THEN prepare a 30 Day report per T.S.3.7.10.2 *

  • SGS Rev. o

~

ECG ATT 23 Pg. 5 of 10

  • D.20 IF one or more of the required low pressure C02 systems becomes inoperable AND the system is not restored to an OPERABLE status within 14 days, THEN prepare a 30 Day report per T.So3.7.10.3~

D.21 IF one or more of the required fire hose stations becomes inoperable, AND the fire hose station(s) is not restored to an OPERABLE status within 14 days, THEN prepare a 30 Day report per (T.S.3.7.10.4) (U2 only).

D.22 IF one or more of the required fire barrier penetrations becomes non-functional AND the non-functional fire barrier penetration is not restored to a functional status within 7 days, THEN prepare a 30 Day report per T.S.3.7.11.

D.23 IF the cumulative operating time at a primary coolant specific activity greater than or equal to 1.0 uCi/gram DEI-131 has exceeded 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6 month

  • D.24 period, THEN prepare a 30 Day report per (T.S.3.4.9a) (U2 only).

IF any Emergency Diesel Generator failure occurs, valid or non-valid, THEN prepare a 30 Day report per (T.S.4.8.1.1.4) (U2 only) and NRC Regulatory Guide 1.108.

LICENSEE' EVENT REPORTS (LERS)

  • CAUTION: *
  • In addition to LER requirements, the below events *
  • or conditions may also require an Immediate Report *
  • or Emergency Declaration. Refer to the ECG Sections *
  • noted in .brackets to ensure total compliance.
  • E.01 IF any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:

(a) Shutdown the reactor and maintain it. in a safe shutdown condition, (b) Remove residual heat,

  • SGS (c)

(d)

Control the release of radioactive material, or Mitigate the consequences of an accident, Rev. 0

ECG ATT 23 Pg. 6 of 10

[Four Hour Report per 10CFR50.72(b) (2) (iii) see ECG Sections 3, 4, or 18]

NOTE:

Events covered above may include one or more personnel errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies.

However, individual component failures need not be reported if redundant equipment in the same system was operable and available to perform the required safety function.

NOTE 10CFR50.72(b) (2) (iii)

a. A single failure in a component required to perform any of the above safety functions is reportable when there is sufficient reason to expect that the failure mechanism is one that could occur in a redundant component.

NOTE 10CFR50.72(b) (2) (iii) cont.

b. Multiple failures of redundant components of a safety system are sufficient reason to expect that the failure mechanism, even though not known, could prevent ~he fulfillment of the safety function.

For example, while the failure of a single rod to scram may not cause a reasonable doubt that other rods would scram, the failure of multiple rods to scram causes a reasonable expectation that other rods may also be affected, and thus, this is an event or condition that could prevent the fulfillment of the safety function, reactor scram *

  • SGS Rev. o,,,

ECG ATT 23 Pg. 7 of 10

  • E.02 IF an event where a single cause or condition resulted in at least one independent train or channel being inoperable in multiple systems, OR two independent trains or channels being inoperable in a single system designed to:

(a) Shutdown the reactor and maintain it in a safe shutdown condition, (b) Remove residual heat, (c) Control the release of radioactive material, or (d) Mitigate the consequences of an accident, THEN prepare an LER per 10CFRS0.73(a) (2) (vii).

NOTE:

For E.03 thru E.11 below, an LER shall be prepared per 10CFRS0.73(a) (2) and the noted subsection thereof.

  • E.03 E.04 E.05 IF plant shutdown is completed as required by Technical Specifications; 10CFRS0.73(a) (2) (i) (A) [see ECG Section 18]

IF any operation or condition prohibited by the plant's Tech Specs; (i) (B) [see ECG Section 18]

IF any deviation from the plant's Tech Specs authorized under 10CFRS0.54(x) or the NRC's regulations; (i) (C) [see ECG Section 18]

E.06 IF any event or condition that resulted iri the condition of the plant, including its principle safety barriers, being seriously degraded or resulted in the plant being:

In an unanalyzed condition that significantly compromised plant safety; (ii) (A)

In a condition that was outside the design basis of the plant; (ii) (B)

In a condition not covered by the plant's operating and emergency procedures. (ii) (C)

[see ECG Section 18]

E.07 IF any natural phenomenon or other external condition that posed an actual threat to the safety of the plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the plant.

10CFRS0.73(a) (2) (iii) [see ECG Sections 8, 12, and 13] ~

SGS Rev. u

~ E~

ATT 23 Pg. 8 of 10

  • E.oa IF any event or condition that resulted in manual or automatic actuating of any Engineered Safety Feature (ESF) ,

including the Reactor Protection System (RPS). However, actuation of an ESF (including RPS) that resulted from and was part of the preplanned sequence during testing or reactor operation need not be reported. 10CFRS0.73(a) (2) (iv) [see ECG Section 18]

E.09 IF any airborne radioactivity release exceeds two times the applicable concentrations of the limits specified in Appendix B, Table II of 10CFR20 of the NRC's regulations in unrestricted areas, when averaged over a time period of one hour. 10CFR50~73(a) (2)(viii) (A) [see ECG Section 7]

E.10 IF any liquid effluent release that exceeded two times the limiting combined Maximum Permissible Concentration (MPC)

(see Note 1 of Appendix B to 10CFR20) at the point of entry into the receiving water in an unrestricted area for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.

10CFR50.73(a) (2) (viii) (B) [see ECG Section 7]

NOTE: (10CFR50.73(a) (2) (ix)

  • E.11 Reports submitted to the NRC, i.a.w. paragraphs (viii) (A) and (viii) (B) above, also meet the effluent release reporting requirements of 10CFR20.

IF any event that posed an actual threat to the safety of the plant or significantly hampered site personnel in the per-formance of the duties necessary for the safe operation of the plant including fires, toxic gas releases, or radioactive releases. 10CFR50.73(a)(2) (x) [see ECG S~ctions 7, 8, or 14].

E.12 IF any violation of the requirements contained in the Operating License except those provisions of Section 2.C.(2) of the License, THEN prepare an LER per License Condition 2I.

E.13 IF the specific activity of the primary coolant is > 1.0 uci/gram DEI-131 or > 100/E uCi/gram, THEN prepare an LER per T.S.3.4.8 (3.4 *. 9).

E.14 IF the results of *steam generator tube inspections fall into Category C-3 and require prompt notification of the NRC, THEN prepare an LER per T.S.4.4.5.5 (4.4.6.5). [see ECG Section 18]

SPEC~AL REPORTS (90 DAYS)

  • F.01 SGS IF the ECCS is actuated and injects water into the Reactor Coolant System, THEN prepare a 90 Day report per T.S.3.5~2 or 3.5.3. [see ECG Section 18]

Rev. o

~ ~

ECG ATT 23 Pg. 9 of 10 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTS G.01 IF there are less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE AND best efforts are unsuccessful in returning the instrument(s) to OPERABLE status within 30 days, THEN explain in the next Semi-Annual Radioactive Release Report per T.S.3.3.3.8.

G.02 IF there are less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE AND best efforts are unsuccessful in returning the instrument(s) to OPERABLE status within 30 days, THEN explain in the next Semi-Annual Radioactive Release Report per T.S.3.3.3.9.

G.03 IF milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required, THEN identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Semi-Annua~ Radioactive Release Report per T.S.3.12.lc.

G.04 IF a land use census is conducted that identifies a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated, THEN identify the new location(s) in the next Semi-Annual Radioactive Release Report per T.S.3.12.2.

G.05 IF a land use census is conducted that identifies a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from where samples are currently being obtained, THEN identify the new location(s) in the next Semi-Annual Radioactive Release Report per T.S.3.12.2.

ANNUAL REPORTS H.01 IF sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination, THEN prepare (or include in, as appropriate) an Annual Report per T.S.4.7.8.1.3 (Ul) or 4.7.8.3. (U2)

H.02 IF an inservice inspection of SG tubes is performed, THEN include the complete results in the Annual Operating Report per T.S.4.4.*5.5 (4.4.6.5) *

  • SGS Rev. O t I

ECG ATT 23 Pg. 10 of 10 H.03 IF analysis has not been performed on radioactive materials supplied as part of the Interlaboratory Comparison Program, THEN report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report per T.S.3.12.3.

H.04 . IF the radiological environmental monitoring program is not being conducted as specified, THEN report the reasons and plans for preventing a recurrence in the Annual Radiological Environmental Operating Report per T.S.3.12.1 *

  • SGS Rev. o

(~

I

.)

ir.'

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