ML031611049

Transmittal of Emergency Response Manual

ML031611049
Person / Time
Site:	Seabrook
Issue date:	06/03/2003
From:	North Atlantic Energy Service Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML031611049 (70)

Text

Seabrook Station - eB Report Date Prlnted: 6/3/03 Transmittal List Requisition No.: R00220 Issued To: C165 DCCINRC WASH OFFSITE (CI65) Date Issued: 613103 Transmittal No.: R002201TR032 issued By: LRB Burke (RMLRB)

Item Document Copy Date Req. Date Ant. Prolect Reason 32 ERI.1 (035/CO) - CLASSIFICATION OF EMERGENCIES CPY0032 00/00/00 00/0000 UPDATE PER CHG INSTR 170 SSER (098)- SORC-STATION EMERGENCY RESPONSE MANUAL CPY0020 00/00/00 00/00/00 UPDATE PER CHG INSTR Name (Block Lettem): slgnature: Date:

Please update your controlled document file with the attached document(s). Slgn and return this transmittal to RMD within 10 work days of the transmittal Issue date. Unless directed otherwise, destroy superseded Retum Address: 02-85 Holder Address: OFF ISSUED BY: LRB Burke (RMLRB) Slgnature: Dae:

IRECEIPT ACKNOWLEDGMENT NOT REQUIRED A

IPrinted y S DOMAIN\RMLR Page of

.r-I

> kooaao CHANGE INSTRUCTIONS EMERGENCY RESPONSE MANUAL (SSER)

Page of 1 r REMOVE I INSERT I Cover Cover Rev. 98 Table of Contents Table of Contents Rev. 98 List of Effective Pages List of Effective Pages Rev. 98 PROCEDURES ER 1.1 (entire) ER 1.1, Classification of Rev. 35 Emergencies

1; RMD Controlled Copy (t 1(o PROGRAM MANUAL Emergency Response Manual SORC Review: 03-024 Date: 5-21-03 Effective Date:

SSER Manual Owner:

Rev. 98 S. Perkins-Grew

i EMERGENCY RESPONSE MANUAL (SSER)

TABLE OF CONTENTS CONTENT PAGE CHAPTER 1: CLASSIFICATION AND RESPONSE

1.0 INTRODUCTION

1-1.1 1.1 General 1-1.1 1.2 Implementation 1-1.1 1.3 Responsibilities 1-1.1 1.4 Definition of Dose 1-1.1 2.0

SUMMARY

OF CHANGES 1-2.1 ER 1.1 Classification of Emergencies ER 1.2 Emergency Plan Activation CIIAPTER2: NOTIFICATION ER 2.0 Emergency Notification Documentation Forms Procedure CHAPTER 3: EMERGENCY FACILITY ACTIVATION ER 3.1 Technical Support Center Operations ER 3.2 Operational Support Center Operations ER 3.3 Emergency Operations Facility Operations ER 3.4 Seabrook Station News Services Operations ER 3.5 Media Center Operations ER 3.6 Assembly Area Operations CHAPTER 4: PERSONNEL PROTECTION ER 4.3 Radiation Protection During Emergency Conditions ER 4.6 Offsite Monitoring and Decontamination Page SSER Rev. 98

CONTENT PAGE CHAPTER 5: RADIOLOGICAL ASSESSMENT ER 5.2 Site Perimeter and Offsite Monitoring and Environmental Sampling ER 5.3 Operation of the MET`PAC System ER 5.4 Protective Action Recommendations ER 5.7 Offsite Dose Projection System Page 2 SSER Rev. 98

e LIST OF EFFECTIVE PAGES PAGE REV. PAGE REV.

Cover 98 TOC 1-2 98 LOEP 98 1-1.1 97 1-2.1 97 ER 1.1 35 ER 1.2 42 ER 2.0 26 ER 3.1 37 ER 3.2 33 ER 3.3 34 ER3.4 16 ER 3.5 24 ER3.6 19 ER 4.3 22 ER 4.6 14 ER 5.2 29 ER 5.3 19 ER 5.4 24 ER 5.7 23 PagelI SSER Rev. 98

i, .

SEABROOK STATION ADMINISTRATIVE PROCEDURE Classification of EmergenciesIl~~~~~~~~~~~~~~~~~~~~~~~~_

..V , . .

ER 1.1 Rev. 35 SORC Review: 03-024 Date: 5-21-03 Effective Date: (e)14 J5 EXPIRATION DATE & 4 6 Procedure Owner:

S. Perkins-Grew

ER 1.1 Page 2 Rev. 35 Contents and Revision Status Contents Page No.

Cover 1 Contents and Revision Status 2 1.0 OBJECTIVES 3 2.0 RESPONSIBILITES 3 2.1 Unit Supervisor 3 2.2 Shift Manager 3 2.3 Site Emergency Director 3 3.0 PRECAUTIONS 3 4.0 PREREQUISITES 5 5.0 ACTIONS 5 5.1 Emergency Classification 5

6.0 REFERENCES

7 7.0 ATTACHMENTS Figure 1 Miscellaneous Emergenicy Conditions and Emergency Action Levels 8 Figure 2 Dose Assessment Data Points 62 Figure 3 Summary of Changes 63 Rev./Chg.

ER 1.1 A Emergency Classification Flow Chart 35

ER 1. Page 3 Rev. 35 1.0 OBJECTIVES This procedure specifies the classification of emergencies in accordance with the Seabrook Station Radiological Emergency Plan (SSREP).

2.0 RESPONSIBILMES 2.1 Unit Supervisor Responsible for assuming the role of Short Term Emergency Director (STED) until the Shift Manager has reported to the Control Room.

2.2 Shift Manager Responsible for classifying observed station conditions in accordance with the emergency classification system specified in this procedure and reclassifying the emergency as necessary until relieved by the Site Emergency Director.

2.3 Site Emergency Director Z.

Responsible for analyzing changing station conditions and reclassifying the egergency classification in accordance with this procedure.

3.0 PRECAUTIONS

1. When two or more critical safety functions (CSFs) or emergency conditions exist and different emergency classifications result, the higher emergency classificaboi will be used.

2. Final emergencyclassifications.arecop$ingent upo teevluation nd,discretion.ofthe Shift Manager or the Site Emergency Director. Thej Sfi, anager ,orSite Emergency Director may make an emergency classification based on clear indications that the event trajectory meets the intent of the initiating cAdit on; althdiigh the ass&iated exhergency action levels have not yet been met or exceeded. .-

3. Critical safety function evaluation for emergency classification purposes should be performed in accordance with the guidance contained in the Emergency Response

'Procedures User's Guide of the Operations Management Manual (OPMM).

4. Critical safety fimction status tree (CSFST) color displays must be sustained indications of continuous conditions. Conditions indicated by CSFST displays must be evaluated and verified using hardwired information before they are used as bases for emergency classifications or for protective action recommendations.

5. Emergency Action Levels (EALs) pertaining to specific initiating conditions are described in Figure 1, Miscellaneous Emergency Conditions and Emergency Action Levels.

ER 1.1 Page 4 Rev. 35

6. When making classifications based upon lights, alarms and other indications, caution must be exercised in the review of these indications to ensure the validity of the information.

7. An emergency classification made by the Short Term Emergency Director is deemed to have been declared when the emergency is announced over the plant paging (Gai-Tronics) system. An emergency reclassification made by the Site Emergency Director (SED) is deemed to have been declared when the SED announces the reclassification in the Control Room or in the Technical Support Center.

8. Once the initial emergency declaration is made the associated ER 1.2 checklist for the Short Term Emergency Director (ER 1.2A, B, C or D) shall be implemented at least through to the completion of state notifications prior to terminating the emergency classification or reclassifying the emergency. If the emergency classification is terminated or if reclassification of the emergency is made after completion of the state notifications, the initial NRC notification must still be made within one hour of the initial classification; however, the initial NRC notification will be for the termination of the emergency or for the emergency classification currently in effect (i.e., the Teclassification).

9. If the emergency-related indications completely clear before a declaration of an emergency classification level has been made, then no emergency classification is required. The Shift Manager shall notify the Emergency News Manager within one hour of the termination of the emergency-related indications that emergency-related indications briefly existed, but cleared prior to the declaration of an emergency classification. The Emergency News Manager will initiate state notifications per good neighbor notification procedures. The event shall be reported to the NRC in accordance with 10 CFR 50.72 and 50.73 per the Regulatory Compliance Manual.

10. If emergency-related indications are received and later cleared, and after the fact it is determined that an emergency classification was warranted out not made, then no emergency classification is required. The Shift Manager shall notify the Emergency News Manager within one hour of discovery that an emergency classification was warranted but not declared and that emergency-related indications no longer exist. The Emergency News Manager will initiate state notifications per good neighbor notification procedures. The event shall be reported to the NRC in accordance with 10 CFR 50.72 and 50.73 per the Regulatory Compliance Manual.

11. If emergency-related indications are received and reduce in severity, such that the emergency classification went from an earlier higher level to a current lower level, the current lower level emergency should be declared. State and NRC notifications shall be made in accordance with Procedure ER 1.2.

ER 1.l Page 5 Rev. 35

12. If emergency conditions are initially classified as an Alert or higher, and then subsequently reclassified to an Unusual Event, all ERO members should continue to report to their facilities. Although activation of the Technical Support-Center, Operational Support Center, and Emergency Operations Facility are not required, the ERO staff will be available to assist with event recovery efforts, interface with State emergency response personnel; and respond to information requests from the media, elected officials and industry organizations.

13. At the discretion of the Shift Manager, the evaluation of EALs 12a, 12b, 12d and 12e may take place after an initial classification is made based on other plant or radiological conditions. If the results of this evaluation indicate that an EAL for a higher emergency classification has been exceeded, then reclassify the emergency and again implement procedure ER 1.2, Emergency Plan Activation. -

14. When the EOF is activated, dose projection results used for classifying emergencies based on the 12 series EALs will normally originate in the EOF. The.EOF will communicate the results to the Site Emergency Director for classification of the emergency. If dose projection results are obtained from another source (e.g., the TSC),

the Site Emergency Director shall direct the Health Physics Coordinator to obtain the concurrence of the EOF Coordinator before reclassifying the emergency based on the 12 seriesEALs. (Protected: Ref. 6.12)-

4.0 PREREQUISITES -

A CSF has been challenged and/or one of-the miscellaneous emergency conditions has occurred.

5.0 ACTIONS , .

Shift Manager/Site Emergency Director 5.1 Emer;ency Classifica,ion.. J .

1. If there has not been avid rea i or sateyme4ti ;ina(s) poceed to Step 5.

2. - 'If there hias beei valid reactor 1rii i st injWe ctn signal(s), determiie whether any of

• the following cintikal safety functiois (CSFs) are chillenged:

S. Subcriticality ..

C. Core cooling H. Heat si&-

P. RCS integity Z. Containinent integrity -

3. Identify the color-coded event for the challenged CSFs.

4. Circle the letter and color of each CSF event or combination of events identified in Step 3 on form ER l.lA, Emergency Classification Flow Chart.

ER 1.1 Page 6 Rev. 35

5. Review and then circle the miscellaneous emergency conditions and combinations of miscellaneous emergency conditions that correspond to actual station conditions on form ER .lA.

6. Circle any combinations of miscellaneous emergency conditions and critical safety functions that correspond to actual station conditions on form ER 1.1A.

7. If emergency classification is being considered under any of the High Radiation EALs, which involve a release, (12a, 12b, 12d or 12e), implement offsite dose assessment using procedure ER 5.7, Offsite Dose Projection System (ODPS). A radiological release that requires dose assessment utilizing the Offsite Dose Projection System (ODPS) is defined as follows:

a. A Wide Range Gas Monitor (WRGM) high alarm (RM-6528-4), or

b. A Main Steam Line Monitor high alarm with an OPEN atmospheric steam dump valve (ASDV) or safety relief valve (SRV) on the affected line, or

c. The results of effluent analysis or site boundary monitoring indicate a dose rate greater than or equal to 0.06 mRem/hr.

In the event of a radiological release via the turbine-driven EFW pump exhaust, dispatch a monitoring team to the downwind site boundary location to obtain a site boundary dose rate and use the Unmonitored Release Path of ODPS.

8. Identify the most severe emergency classification that corresponds to the events circled on form ER 1.I A. Refer to the corresponding Figure 1 initiating condition to complete classification.

9. If an emergency classification is warranted, immediately implement Station Emergency Response Procedure ER 1.2, Emergency Plan Activation.

NOTE This action is not applicable after the Technical Support Center is activated at an Alert or higher classification.

ER 1.1 Page 7 Rev. 35

6.0 REFERENCES

1. Seabrook Station Radiological Emergency Plan

2. ER 1.2, Emergency Plan Activation

3. ER 5.7, Offsite Dose Projection System

4. ECA-1.1, Loss of Emergency Coolant Recirculation

5. ECA-1.2, LOCA Outside of Containment

6. E-1, Loss of Reactor or.Secondary Coolant

7. E-2, Faulted Steam Generator Isolation

8. E-3, Steam Generator Tube Rupture

9. ES-0. 1, Reactor Trip Response

10. ES-1.l, SI Termination

11. OS1000.11, Post-Trip to HotStandby

12. SEP #20000030, Response to A/R 00004326 from CR #00-1882

~~~. .

ER1.1 Page8 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels Initiating Condition for UNUSUAL EVENT 6a. Buses E5 AND E6 are not powered from an offsite source for greater than 15 minutes.

EMERGENCY ACTION LEVELS BUSES E5 AND E6 ARE NOT POWERED FROM AN OFFSITE SOURCE FOR GREATER THAN 15 MINUTES.

NOTE The emergency action level does not apply to testing situations where either Bus E5 or E6 is being powered by its respective diesel generator.

IF condition 6a (above) exists concurrently with condition 7a (below), an ALERT shall be declared.

7a. Primary to secondary leakage greater than 500 gallons per day from any steam generator or steam generator specific activity greater than 0.1 Ci/cc dose equivalent I-13 1.

EMERGENCY ACTION LEVELS

1. ANY INDICATION OF PRIMARY TO SECONDARY LEAKAGE EXCEEDING 500 GALLONS PER DAY FROM ANY STEAM GENERATOR OR

2. ANALYSIS OF A BLOWDOWN LIQUID SAMPLE BY THE CHEMISTRY DEPARTMENT INDICATES ACTIVITY GREATER THAN 0.1 ZICi/cc DOSE EQUIVALENT I-131.

IF condition 6a (above) exists concurrently with condition 7b (below), a SITE AREA EMERGENCY shall be declared.

7b. Steam Generator Tube Rupture (E-3)

EMERGENCY ACTION LEVELS NITIATION OF EMERGENCY PROCEDURE E-3, STEAM GENERATOR TUBE RUPTURE.

ER 1.1 Page 9 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 6b. Bus ES AND E6 cannot be powered from the diesels.

NOTE This Initiating Condition does not apply in Modes 5 or 6, br when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. BOTH INDICATING LIGHTS MCB-HF UL-19 "A" DIESEL NOT AVAILABLE UL-20 "B" DIESEL NOT AVAILABLE

-X .

2. BOTH VAS ALARMS FPOIN-F6587 DG TRAIN A EMRG PWR INOP F6637 DG TRAIN B EMERG PWR INOP

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ER 1.1 Page 10 Rev. 35 Figure 1 Miscel!aneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 6c. Bus E5 AND E6 cannot be powered from the diesels or an offsite source.

EMERGENCY ACTION LEVELS

1. BOTH HARDWIRE ALARMS MCB-HF UA-54 4160V BUS 5 VOLTS LO UA-55 4160V BUS 6 VOLTS LO OR

2. BOTH VAS ALARMS F POINT MESSAGE F7300 BUS E5 LOSS OF POWER F7310 BUS E6 LOSS OF POWER AND

3. BOTH NDICATING LIGHTS MCB-HF UL-l 9 "A" DIESEL NOT AVAILABLE UL-20 "B" DIESEL NOT AVAILABLE OR

4. BOTH VAS ALARMS F POINT F6587 DG TRAIN A EMERG PWR INOP F6637 DG TRAIN B EMERG PWR INOP

ER1.1 Page I Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 6d. Loss of all vital DC Busses 11A, I1B, 1IC and l1D.

EMERGENCY ACTION LEVELS

1. ALL THE FOLLOWING VAS ALARMS D6094 DC BUS 11A VOLT LO-LO D6095 DC BUS IC VOLT LO-LO D6096 DC BUS IB VOLT LO-LO D6097 DC BUS lID VOLT LO-LO OR

2. ALL OF THE FOLLOWING HARDWIRED ALARMS:

UA-54 DC BUS 1 A VOLT LO DC BUS 11C VOLTLO UA-55 DC BUS lB VOLT LO DC BUS lID VOLT LO

,I

. t.- .

ER 1.1 Page 12 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 6e. Bus E5 AND E6 cannot be powered from the diesels or an offsite source within 15 minutes.

NOTE This Initiating Conditicn does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. BOTH HARDWIRE ALARMS MCB-HF UA-54 4160V BUS 5 VOLTS LO UA-55 4160V BUS 6 VOLTS LO NOTE: IF ONE OF THESE HAS CLEARED (LIGHT OUT), A BUS IS REENERGIZED AND

2. NO ALARM HAS BEEN CLEAR ED WYITHIN FIFTEEN MINUTES.

IF condition 6e exists concurrently with an H red or Z orange, a GENERAL EMERGENCY shall be declared.

IF conditions 6e and 6f exist concurrently, refer to condition 6e AND 6f.

ER 1.1 Page 13 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY . I 6f LossofvitalDCBusses lA, IIB, ilCand llDforgreaterthan l5minutes.

NOT'E This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS . - -  :

I. ALL OF THE FOLLOWING HARDWIRE ALARMS: -.. ; I UA-54 DC BUS llA VOLT LO DC BUS IC VLL LO VOLT UA-55 DC BUS-.I OB LO VOLT DC-BUS I1lD - A- V'OL-N LO OR

2. ALL OF THE FOLLOWING VAS ALARMS:

-D6094 DCBS1IA - VOLTLO-LO----

.. .D.6095. - - B .US .DC llC V_LOI.

'D696- DC IiB -;'V

-BUS O-LO ' .

D6097 DC BUS 1ID VOLT LO-LO AND l 3. NO ALARM HAS BEEN CLEARED WITHIN FIFTEEN MNUTES. I IF conditions 6f and 6e exist concurrently, refer to condition 6e AND 6f.

ER 1.1 Page 14 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for GENERAL EMERGENCY 6e. Bus E5 AND E6 cannot be powered from the diesels or an offsite source within 15 minutes.

AND 6f. Loss of all vital DC busses 1 A, 11 B, 1IC, and 1 D for greater than 15 minutes.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS AN EVENT HAS OCCURRED THAT INDICATES A LOSS OF BUS E5 AND BUS E6, AND A LOSS OF ALL VITAL DC BUSSES 1IA, IIB, IIC, I ID FOR GREATER THAN 15 MINUTES. THIS MAY BE INDICATED BY A LOSS OF ALL PUMPS AND VALVE LIGHTS, STATUS LIGHTS, HARDWIRE INDICATIONS, ETC.

ER 1.1 Page 15 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT if Condition 6a also exists 7a. Primary to secondary leakage greater than 500 gallons per day from any steamn generator or steam generator specific activity greater than 0.1 pCi/cc dose equivalent I-131.

AND 6a. Buses E5 AND E6 are not powered from an offsite source for greater than 15 minutes.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS .

1. -.ANY INDICATION OF PRIMARY TO SECONDARY LEAKAGE EXCEEDING 500 GALLONS PER DAY FROM ANY STEAM GENERATOR OR

2. ANALYSIS OF A BLOWDOWN LIQUID SAMPLE BY THE CHEMISTRY DEPARTMENT INDICATES ACTIVITY GREATER THAN 0.1 jiCi/cc DOSE EQUIVALENT -131 AND

3. BUSES ES AND E6 ARE NOT POWERED FROM AN OFFSITE SOURCE FOR GREATER THAN 15 MINUTES.

ER 1.1 Page 16 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 7b. Steam Generator Tube Rupture NOTE l This Initiating Condition does not apply in Modes 4, 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS l1 IUTIATION OF EMERCFNCY PROCEDURE E-3, STEAM GENERATOR TUBE l RUPTURE.l OR

2. INITIATION OF ABNORMAL PROCEDURE OS 1227.02, STEAM GENERATOR TUBE LEAK.

AND

3. A SECOND CHARGING PUMP HAS BEEN STARTED.

IF condition 7b (above) exists concurently with condition 6a (below), a SITE AREA EMERGENCY shall be declared.

6a. Buses E5 AND E6 are not powered from an offsite source for greater than 15 minutes.

EMERGENCY ACTION LEVELS BUSES E5 AND E6 ARE NOT POWERED FROM AN OFFSITE SOURCE FOR GREATER THAN 15 MINUTES.

IF condition 7b (above) exists concurrently with condition 8b (below), a SITE AREA EMERGENCY shall be declared.

8b. Reactor coolant gross activity greater than or equal to 3,000 pCi/cc or dose equivalent 1-131 activity greater than or equal to 300 plCi/cc.

ER.l Page17 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action' Levels (Continued)

Initiating Condition for ALERT (continued)

EMERGENCY ACTION LEVELS

1. REACTOR COOLANT GROSS ACTIITY IS GREATER THAN OR EQUAL TO 3000 Ci/cc AS DETERMINED BY CHEMISTRY DEPARTMENT PERSONNEL PER CS0925.01 OR CS0925.16 OR

2. REACTOR COOLANT DOSE EQUIVALENT 1-131 IS GREATER THAN OR EQUAL TO 300 Ci/cc AS DETERMNED BY CHEMISTRY DEPARTMENT PERSONNEL PER CS0925.01 OR CS0925. 16. .

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ER 1.l Page 18 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 8a. Reactor coolant specific activity greater than Technical Specification limits.

NOTE This Initiating Condition does not apply in Modes 3 (with Tavg less than 500°F) 4, 5 and 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. CHEMISTRY DEPARTMENT SAMPLING RESULTS INDICATE THAT THE SPECIFIC ACTIVITY OF THE REACTOR COOLANT IS GREATER THAN-I j.Ci/gm DOSE EQUIVALENT IODINE 1-131 FOR MORE THAN 48 HOURS DURING ONE CONTINUOUS TIME INTERVAL OR

2. CHEMISTRY DEPARTMENT SAMPLING RESULTS INDICATE THAT THE DOSE EQUIVALENT IODINEF I-131 PRIMARY COOLANT SPECIFIC ACTIVITY IS EXCEEDING THE LIMIT LINE SHOWN IN TECHNICAL SPECIFICATION FI(GURE 3.4-1 OR

3. CHEMISTRY DEPARTMENT SAMPLING RESULTS INDICATE THAr THE SPECIFIC ACTIVITY OF THE REACTOR COOLANT IS GREATER THAN 100/E pCi/gm.

ER 1.1 Page 19 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 8b. Reactor coolant gross activity greater than or equal to 3,000 ,uCi/cc or dose equivalent 1-131 activity greater than or equal to 300 pCi/cc.

EMERGENCY ACTION LEVELS 1 REACTOR COOLANT GROSS ACTVITY IS GREATER THAN OR EQUAL TO 3000 jICi/cc AS DETERMINED BY CHEMISTRY DEPARTMNT PERSONNEL PER CS0925.01 OR CS0925.16 OR

2. REACTOR COOLANT DOSE EQUIVALENT 1-131 IS GREATER THAN OR EQUAL TO 30 pCi/cc AS DETERMNEDBY CHEMISTRY DEPARTMENT PERSONNEL PER CS0925.01 OR CS0925.16..-

IF condition 8b (above) exists concurrently with condition 7b (below), a SITE AREA EMERGENCY shall be declared.

7b. Steam.Generator Tube Rupture (E-3)

I* *. . . I !..II I I - . ..

This Initiating Condition does not apply in Modes 4,5-oi 6, or vhen the reactor vessel is e..._._._. ..... .

,,e ......................................

EMERGENCY ACTION LEVELS JNITIAON OF EMERGENCY PROCEDURE f-3? STEAM GENERATOR TUBE IRUPTURE. S I ., . -:. , . ,-- I

- - -' ki . .-. , 1 I ,

ER 1.1 Page 20 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Leveis (Continued)

Initiating Condition for SITE AREA EMERGENCY 8c. Containment post-LOCA monitors reading greater than or equal to 1,000 R/hr.

EMERGENCY ACTION LEVELS CONTAINMENT DOSE RATES ARE GREATER THAN OR EQUAL TO 1,000 RIHR AS INDICATED BY BOTH RM-6576A AND RM-6576B.

NOTE If one channel is inoperable, the reading on the operable channel should be verified by a rise in or off-scale high readings on cther containment monitors or personnel hatch monitor.

ER 1.1 Page 21 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Iitiating Condition for GENERAL EMERGENCY 8d. Containment post-LOCA monitors reading greater than or equal to 4,000 R/hr.

EMERGENCY ACTION LEVELS CONTAINMENT DOSE RATES ARE GREATER THAN OR EQUAL TO,.

4,000 R/IHR AS INDICATED BY BOTH RM-6576A-AND RM-6576B.'

NOTE If one channel is inoperable, the reading on the operable channel shouldbe.verified by a rise in or off-scale high readings-on other containment monitors or personnel hatch monitor.

ER 1.1 Page 22 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 9a. Unplanned loss of most UA panel hardwired annunciator alarms for greater than 15 minutes.

NOTE This Initiating Condition does not apply in Mode 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. MOST OR ALL UA PANEL HARDWIRED ANNUNCIATOR ALARMS HAVE BEEN LOST FOR GREATER THAN 15 MINUTES AND

2. COMPENSATORY INDICATIONS ARE AVAILABLE (E.G., MAIN CONTROL BOARD INDICATIONS, MPCS, VAS, SPDS, ETC.)

AND

3. THE LOSS OF THE UA PANEL HARDVWIRED ANNUNCIATOR ALARMS REQUIRES INCREASED SURVEILLANCE TO SAFELY OPERATE THE STATION AND

4. THE LOSS OF THE UA PANEL HARDWIRED ANNUNCIATOR ALARMS DID NOT RESULT FROM A PLANNED ACTION.

ER 1.1 Page 23 Rev. 35 Figure Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 9b. Failure of Control Room RDMS panels EMERGENCY ACTION LEVELS I. CP-180A INDICATES BLANK OR ERRONEOUS LED DISPLAYS AND

2. CP-180B INDICATES BLANK OR ERRONEOUS-LED DISPLAYS -

AND -' ' ' ' - -'

3. CP-295 RDMS TERMENAL INDICATES BLANK. OR ERRONEOUS CRT DISPLAY.

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ER 1.1 Page 24 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 9c. Loss of automatic and manual SPDS.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. LOSS OF A COMPUTER SPDS FUNCTION (e.g., the C tree)

AND

2. LOSS OF BOTH TRAINS OF HARDWIRED INDICATIONS FOR AN SPDS FUNCTION AND

3. THE LOSS OF THE SPDS FUNCTION DID NOT RESULT FROM A PLANNED ACTION.

, _ _ _ _ - _- - ,~~~--

NOTE This Initiating Condition does not apply when the Pressurized Thermal Shock (P) status tree is unreliable due to wide range T,01d being unavailable (Ref. UFSAR, Chapter 7, Appendix 7A, deviation #7 to Regulatory Guide 1.97).

This exception assumes that plant conditions support using saturation temperature for Steam Generator (S/G) pressure as an alternate indication. The use of S/G parameters is acceptable only when

• the S/G being used is not faulted, and

• the S/G is "coupled" to the RCS (e.g., S/G pressure is less than or equal to RCS pressure).

ER 1.1 Page 25 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 9d. Unplanned loss of most UA panel hardwired annunciator alarms for greater than 15 minutes with a transient in progress OR without compensatory measures.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS I1. MOST OR ALL UA PANEL HARDWIRED ANNUNCIATOR-ALARMS HAVE BEEN LOST FOR GREATER THAN 15 MINUTES

.- " ~AND --

2. THE'LOSS OF THE UA PANEL HARDWIRED ANNUNCIATOR ALARMS REQUIRES INCREASED SURVEILLANCES TO SAFELY OPERATE THE STATION

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A.

AND ...

l3. THE LOSS OF THE UA PANEL HARDWIRED ANNUNCIATOR ALARMS

DID NOT RESULTTROM A PLANNED-ACTION...

4. COMPENSATORY INDICATIONS ARE NOT-AVARIABLE (EJQG., MAIN CONTROL BOARD INDICATIONS, MPCS, SPDS, VAS, ETC.)

'. SIGN"iCAT A P TT ORR I , ,.

5. A SIGNIFICANT PLANT TRANSIENT IS IN PROGRESS.

ER 1.1 Page 26 Rev. 35 Figure 1 Miscella-aeous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 9e. Inability to monitor a significant transient in progress.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. MOST OR ALL UA PANEL HARDWIRED ANNUNCIATOR ALARMS HAVE BEEN LOST AND

2. COMPENSATORY INDICATIONS ARE NOT AVAILABLE (E.G., MAIN CONTROL BOARD INDICATIONS, MPCS, SPDS, VAS, ETC.)

AND

3. A SIGNIFICANT PLANT TRANSIENT IS IN PROGRESS. I

ER 1.1 Page 27 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 10a. Loss of all control room communication.

EMERGENCY ACTION LEVELS COMPLETE LOSS OF ALL THE FOLLOWING CONTROL ROOM COMMUNICATIONS:

a. TELEPHONES, INCLUDING THOSE ON CP-295 AND

b. RADIOS, INCLUDING THE MANCHESTER DISPATCHER AND

c. GAITRONICS AND

d. SOUND POWERED PHONES.

.~~ I

ER 1.1 Page 28 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT I la. Initiation of shutdown to the cold shutdown condition as required by technical specifications.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. THE TECHNICAL SPECIFICATION IN QUESTION REQUIRES THE STATION TO ULTIMATELY ACHIEVE COLD SHUTDOWN (MODE 5)

AND

2. THE PRIMARY SYSTEM TEMPERATURE IS BEING REDUCED AND

3. THE TIME REMAING TO REACH ANY REQUIRED MODE IS LESS THAN OR EQUAL TO ZERO. RPF'.R TO ODI.30 FOR TIME CALCULATION INSTRUCTIONS.

ER 1.l Page 29 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 12a. Site boundary dose rate greater than or equal to 0.06 mRem/hr.

EMERGENCY ACTION LEVELS

1. DOSE PROJECTIONS OR EFFLUENT ANALYSIS INDICATES A PROJECTED TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) RATE GREATER THAN OR EQUAL TO 0.06 mRem/hr AT THE SITE BOUNDARY OR

2. FIELD'MONITORING INDICATES A DOSE RATE GREATER THAN OR EQUL TO 0:06-nRern/hrAT THE SITE BOUNDARY (SEE NOTE 1).

NOTE 1-This value is-alternately called the "whole body" dose rate or "deep dose equivalent" rate. It is typically a "closed window" reading.

)

• N.1TE . T a-TTE Figure2 provides computer-generated assessment poitsand_RDMS channtumbers to be used for dose assessment.

ER 1.1 Page 30 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 12b. Site boundary dose rate greater than or equal to 0.6 mRernhr.

EMERGENCY ACTION LEVELS

1. DOSE PROJECTIONS OR EFFLUENT ANALYSIS INDICATES A PROJECTED TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) RATE GREATER THAN OR EQUAL TO 0.6 mRem/hr AT THE SITE BOUNDARY OR

2. FiELD MONrrORING INDICATES A DOSE RATE GREATER THAN OR EQUAL TO 0.6 mRem/hr AT THE SrrE BOUNDARY (SEE NOTE I).

NOTE 1 This value is alternately called the "whole body' dose rate or "deep dose equivalent" rate. It is typically a "closed window" reading.

NOTE 2 Figure 2 provides computer generated assessment points and RDMS channel numbers to be used for dose assessment.

ER 1.1 Page 31 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 12c. Significant loss in control of radioactive materials and an increase in radiation monitor(s) by a factor of 1000 or greater.

EMERGENCY ACTION LEVELS

1. UNEXPECTED INCREASE IN AN AREA RADIATION MONITOR(S) BY A FACTOR OF 1000 OR GREATER AND

2. A SIGNIFICANT LOSS IN THE CONTROL OF RADIOACTIVE MATERIALS HAS OCCURRED.

NOTE To determine a factor of 1000 increase, select he,,ippropate trend display,on the alanning channel(s) to ascertain the rate of incare4w..and app ovcimate background value.

If needed, verify the increase by survey or other means to confirm that the increase is a result of-a significant loss in control of radioactive material.

_)A. }/

ER 1.1 Page 32 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 12d. Site boundary dose rate greater than or equal to 50 mRem/hour, or adult thyroid committed dose equivalent rate greater than or equal to 250 mRem/hour.

EMERGENCY ACTION LEVELS

1. DOSE PROJECTIONS OR EFFLUENT ANALYSIS INDICATES A PROJECTED TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) RATE GREATER THAN OR EQUAL TO 50 mRem/hr AT THE SITE BOUNDARY OR

2. DOSE PROJECTIONS OR EFFLUENT ANALYSIS INDICATE A PROJECTED ADULT THYROID COMMITTED DOSE EQUIVALENT (CDE) RATE GREATER THAN OR EQUAL TO 250 nRerrJhr AT THE SITE BOUNDARY OR

3. FIELD MONITORING INDICATES A DOSE RATE GREATER THAN OR EQUAL TO 50 mRem/hr AT THE SITE BOUNDARY (SEE NOTE 1)

OR

4. FIELD MONITORING RESULTS INDICATE AN ADULT THYROID COMMIUTED DOSE EQUIVALENT (CDE) RATE GREATER THAN OR EQUAL TO 250 mRemr/hr AT THE SITE BOUNDARY.

NOTE 1 This value is alternately called the "whole body" dose rate or "deep dose equivalent" rate. It is typically a "closed window" reading.

NOTE 2 Figure 2 provides computer generated assessment points and RDMS channel numbers to be used for dose assessment.

ER 1.1 Page 33 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for GENERAL EMERGENCY 12e. Site boundary Total Effective Dose Equivalent greater than or.equal to 1,000 mRem or Adult Thyroid Committed Dose Equivalent greater than or equal to 5,000 mRem.

EMERGENCY ACTION LEVELS

1. DOSE PROJECTIONS OR EFFLUENT ANALYSIS IDICATES A TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) OF GREATER THAN QR EQUAL TO 1,000 mRem AT THE S1TE BOUNDARY FOR THE ACTUAL OR PROJECTED DURATION OF THE RELEASE OR

2. DOSE PROJECIONS OR EFFLUENT ANALYSIS INDIOATES ANADULT THYROID COMmrTmED DOSE EQUIVALENT (CDp,) OF GREATER THAN OR EQUAL TO 5,000 imRem AT THE SITE BOUNDARY FOR THE ACTUAL OR PROJECTED DURATION OF THE RELEASE OR

3. FIELD MONITORINGRESI IDIC4TE A DEEP OSEEQA (DDE)

OF GREATER THAN OR EQUALTO10..000jRlmm AT TUE SITE BOUNDARY FOR THE ACTUAL OR PROJECTED DURATION OF THE RELEASE (SEE NOTE 1)

4. FIELD MONITORING RESULTS INDICA¶TE AN ADlLT THYROID COMMITED DOSEEQUWVALENT(CDE) OF GREATERTHAN OR-EQUAL TO 5-,000 dRem AT THE SITE-BOUNDARY FOR THE ACTUAL ORPROJECTED, DURATION OF THE RELEASE. .

ri: -. v' ' . . >. - .- ' . - ! - U:...

NQTE'I ,.l;.: XtZ[

This value is also called-the 'whok body" dose. It is typically based on-a "closed window" reading.

. . ,,,I , - ,.

NOTE 2 Figure 2 provides computer generated assessment points and RDMS channel numbers to be used for dose assessment.

ER 1.1 Page 34 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 13a. Fuel handling accident with release of radioactivity.

EMERGENCY ACTION LEVELS

1. NOTIFICATION OF THE DROPPING, BUMPING, OR OTHERWISE ROUGH HANDLING OF AN IRRADIATED FUEL ASSEMBLY AND

2. ANY INDICATION THAT RADIOACTIVITY HAS BEEN RELEASED FROM THE IRRADIATED FUEL ASSEMBLY. THESE INDICATIONS MAY INCLUDE:

• ALARMS OR ELEVATED READINGS ON AREA RDMS MONITORS

- CONTAINMENT MONITORS: RM-6535A or RM-6535B

- FUEL STORAGE BLDG MONITORS: RM-6549 OR RM-6518

• ALARMS OR ELEVATED READINGS ON PORTABLE RADIATION MONITORS

• ALARMS OR ELEVATED READINGS ON AIR MONITORS AND

3. A VISUAL ASSESSM1ENT OF THE IRtADIATED FUEL ASSEMBLY INDICATES NO MAJOR DAMAGE OR DEFORMATION (E.G., NO CRUSHED OR BENT FUEL RODS, ALL RODS REMAIN WITHIN THE ASSEMBLY FRAME, ETC.)

OR

4. A VISUAL ASSESSMENT OF THE EXTENT OF DAMAGE TO THE IRRADIATED FUEL ASSEMBLY CANNOT OR HAS NOT BEEN MADE.

ER 1.1 Page 35 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 13b. Major damage to irradiated fuel with radiation release or loss of water in spent fuel pool or reactor cavity and irradiated fuel present.

EMERGENCY ACTION LEVELS

1. NOTIFICATION OF THE DROPPING, BUMPING, OR OTHERWISE ROUGH HANDLING OF AN IRRADIATED FUEL ASSEMBLY AND.

2. ANY INDICATION THAT RADIOACTIVITY HAS BEEN RELEASED FROM THE IRRADIATEI)FUEL ASSEMBLY. THESE INDICATIONS MAY INCLUDE:

ALARMS OR ELEVATED READINGS ON AREA RDMS MONITORS

- CONTAINMENT MONITt)RS- RM-6535A or RM-6535B

- FUEL STORAGE BLDG MONITORS: iM-6549 OR RM-6518 e ALARMS OR ELEVATED RiADINGS ON PORTABLE RADIATION MONITORS

• :ALARMSJOR ELEVAIEI RJEADINGS ON AIRMOITORS ANP-,  !

3. A VISUAL ASSESSMENT OF THE IRRADIATED FUEL ASSEMBLY INDICATES MAJOR DEFORM RTIP DARAMAE-(E.G., CRUSHED OR BENT FUEL RODS, ALL RODSWOT WIN THEASSEMBLY RAME, ETC.) - -

OR Ii : (Continued on next page)' - - -

ER1.l Page36 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY

4. a) THE FOLLOWING VAS ALARM:

D5198 SPENT FUEL POOL LEVEL LOW AND b) THE INABILITY TO MAINTAIN LEVEL AS INDICATED BY AN UNCONTROLLED DECREASING LEVEL READ ON SF-LI-2607 (MCB-BR)

AND c) IRRADIATED FUEL IS PRESENT IN THE POOL AND UNCOVERY IS IMMINENT OR HAS OCCURRED OR

5. a) THE FOLLOWING VAS ALARM:

B7062 RX REFUEL CAVITY LEVEL LOW AND b) THE INABILITY TO MAINTADI LEVEL AS INDICATED BY AN UNCONTROLLED DECREASING LEVEL READ ON SF-LI-2629 (MCB-BF)

AND c) IRRADIATED FUEL IS PRESENT IN THE CAVITY AND UNCOVERY IS MMINENT OR HAS OCCURRED.

ER 1.1 Page 37 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 14a. Abnormal reactor trip or safety injection.

NOTE This Initiating Condition does not apply in Modes 4, 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. ENTRY INTO PROCEDURE ES-0. 1, REACTOR TRIP RESPONSE, WITHOUT TRANSITIONING T.O,PROCEDURE OS1OOO.11, POST-TRIP TO HOT STANDBY OR,

2. ENTRY INTO PROCEDURE ES-1.1, SI TERMINATION, WITHOUT TRANSTlONING TO PROCEDURE OS1000.11, POST-TRIP TO HOT STANDBY OR .

3. TRANSIONING BACK' StO PkOt P E-, 1EACTOR TRIP OR SAFETY iNJEtCTION, FROM PRCtEDRE W-S 1;`8ESPONSE TO NUCLEAR POWER GENERATION/ATWS.

. I

- IV , , I !i , I

-r . . I 1- . - . I

ER 1.1 Page 38 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 15a. Reactor coolant system leakage.

NOTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. UNIDENTIFIED OR PRESSURE BOUNDARY LEAKAGE GREATER THAN 10 GPM OR

2. IDENTIFIED LEAKAGE GREATER THAN 25 GPM.

NOTE Emergency Action Level number 2 includes Reactor Coolant System (RCS) leakage to a steam generator (i.e., primary to secondary leakage).

ER 1.1 Page 39 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 15b. Faulted Steam Generator Isolation (E-2). ,

NQTE This Initiating Condition does not apply in Modes 5 or 6, or when the reactor vessel is defueled. .

EMERGENCY ACTION LEVELS INITIATION OF EMERGENCY PROCEDURE E-2, FAULTED STEAM GENERATOR ISOLATION. J

ER 1.1 Page 40 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 15c. Reactor coolant leak rate greater than 50 gpm.

l ~~~NOTEl This Init.ating Condition does not apply when the reactor vessel is defueled. I EMERGENCY ACTION LEVELS REACTOR COOLANT LEAK RATE GREATER THAN 50 GPM. 7 NOTE This Initiating Condition does not apply to Reactor Coolant System (RCS) leakage to a steam generator (i.e., primary to secondary leakage). Conditions where RCS leakage is to a steam generator should be evaluated against Emergency Action Levels for Initiating Conditions 7a or 7b.

ER 1.1 Page 41 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 15d. Loss of Reactor Coolant with ECCS required.

NOTE This Initiating Condition does not apply in Modes 4, 5 or 6, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. INIATIONOFEMERGENCYPROCEDUREE-1,LOSSOFREACTOROR SECONDARY COOLANT . Ie AND

2. RCS SUBCOOLINGBASEDONCOREEXITTHERMOCOUPLES-IS'LESS

- THAN 40-- t-OR

3. PRESSURIZER LEVEL IS LESS THAN OR EQUAL TO 5% (35% IF CONTAINMENT PRESSURE IS GREATER THAN 4 PSIG).

ER 1.1 Page 42 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiatin- Condition for SITE AREA EMERGENCY 15e. LOCA outside of contaimnent NOTE This Initiating Condition does not apply when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. INITIATION OF EMERGENCY PROCEDURE ECA-1.2, LOCA OUTSIDE OF CONTAINMENT ]

OR

2. RCS PRESSURE IS DECREASING UNCONTROLLABLY AND

3. ANY COMBINATION OF PLANT PARAMETERS THAT INDICATE THAT THE RCS MASS IS BEING LOST OUTSIDE THE CONTAINMENT BOUNDARY.

NOTE If this condition exists concurrently with a C orange, declare a GENERAL EMERGENCY. Refer to the CSFST EALs at the top of Form ER 1.IA.

ER 1.1 Page 43 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for GENERAL EMERGENCY 15f. Loss of emergency coolant recirculation (ECA-1.1). 1-NOTE This Initiating Condition does not apply in Modes 4, 5 or 6, or,when the reactor vessel is defueled.

. j EMERGENCY ACTION LEVELS lNlTIATION OF EMERGENCY PROCEDURE ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCLTION.N

1 I

ER 1.1 Page 44 Rev. 35 Figure 1 Miscellaneous Einergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 16a. Fire inside the Protected Area lasting more than 0 minutes EMERGENCY ACTION LEVELS

1. THERE IS A FIRE LOCATED INSIDE THE PROTECTED AREA (See Note below)

AND

2. THE FIRE IS NOT EXTINGUISHED WMHIN 10 MINUTES OF CONTROL ROOM NOTIFICATION OR VERIFICATION OF A CONTROL ROOM ALARM.

NOTE Fire as detected by visual observation and reported by plant personnel or sensor alarm indication. The 10 minute time period begins with a credible notification that a fire is occuning, or verification (by whatever means) that the fire detection system alann is valid. , .

ER 1.1 Page45 Rev. 35 Figure I Miscellaneous Emergency Conditions and Emergency Acti'on Levels (Continued)

Initiating Condition for ALERT 16b. Fire potentially or actually defeating one train of a safety system EMERGENCY ACTION LEVELS I. A VALID "S" OR "P" SIGNAL EXISTS AND

2. THE FIRE HAS DISABLED, OR HAS THE POTENTIAL TO DISABLE, ONE OPERABLE TRAIN OF ANY OF THE FOLLOWING SYSTEMS:

a) Charging b) Safety Injection c) Residual Heat Removal d) Contaimnent Building Spray e) Emergency Feedwater f) Contaimnent Phase A Isolation Valves g) -ontainment Phase-B Isolation Valves (SEE NOTE BELOW)

NOTE If the remaining (unaffected by the fire) train is also inoperable, refer to Initiating Condition 16c.

ER 1.1 Page 46 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 16c. Fire potentially or actually defeating both, trains of a safety system EMERGENCY ACTION LEVELS

[ A VALID "S" OR "P" SIGNAL EXISTS AND

2. THE FIRE HAS RESULTED, OR MAY RESULT, IN THE LOSS OF BOTH TRAINS OF ANY OF THE FOLLOWING SYSTEMS:

a) Charging b) Safety Injection c) Residual Heat Removal d) Containment Building Spray e) Emergency Feedwater (If the Startup Feedwater System is operable, declare an ALERT.)

f) Containment Phase A Isolation Valves g) Containment Phase B Isolatior. Valves

ER 1.1 Page 47 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 17a. Control Room evacuation anticipated or required with safe shutdown capability established.

EMERGENCY ACTION LEVELS A detennination by the Shift Manager that:

CONTROL ROOM EVACUATION IS ANTICIPATEDl C2R ,

CONTROL ROOM EVACUATION HAS OCCURRED AND SAFE SHUTDOWN CAPABILITY HAS BEEN ESTABLISHED WITHN 15 MINUTES OF THE ANNOUNCEMENT FOR MANNING THE REMOTE SAFE SHUTDOWN PANELS PER PROCEDURE OS 1200.02.

l~~~~~  !: . ~~ ~ ~ ~~~

. ~ ~ ~ ~~~~~~~~~~~~~~~~~~~~~~~~

. I NOTE 1 In the event of a Control Room evacuation, Sh6rt TermEnergency Director (STED) actions may be peiformed from the Alteiiate TSC in Adrninistration Building Room 219. If time permits, take the STED packet from the Control Room with you; if not, SSER Manual checklists and forms are available in a file cabinet in Room 219.

Announce that TSC personnel should assemble in Room 245 of the Administration Building and await further instructions.

NOTE 2 Verify that Remote Safe Shutdown (RSS) capability was established within 15 minutes of the announcement to man the RSS panels; if not, declare a Site Area Emergency in accordance with Initiating Condition 17b. RSS capability is established when at least one RSS panel is manned.

ER 1.1 Page 48 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 17b. Control Room evacuation without safe shutdown capability established within fifteen minutes.

EMERGENCY ACTION LEVELS A determination by the Shift Manager that the following conditions exist:

I1. THE CONTROL ROOM HAS BEEN EVACUATED AND

2. SAFE SHUTDOWN CAPABILITY HAS NOT BEEN ESTABLISHED WITHIN 15 MINUTES OF THE ANNOUNCEMENT FOR MANNING THE REMOTE SAFE SHUTDOWN PANELS PER PROCEDURE OS1200.02.

ER 1.1 Page 49 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Coniued)

Initiating Condition for UNUSUAL EVENT 18a. Hazards experienced or projected which involve potential degradation of station safety.

EMERGENCY ACTION LEVELS NATURAL PHENOMENA ANY SEISMIC ACIVITY LESS THAN OBE LEVELS AS INDICATED BY:

a) VAS ALARM D POlNT MESSAGE 5452 SEISMIC EVENT IN-PROGRESS AND b) YELLOW "EVENT" LIGHT LIT AND RED "OBE" LIGHT OFF ON SEISMIC MONITORING CONTROL CABINET 1-SM-CP-58 POWER PANEL AND c) EITHER OF THE FOLLOWING:

(1) THE EARTHQUAKE IS FELT BY STATION PERSONNEL OR (2) THE EARTHQUAKE OCCURRENCE IS VERIF1ED DURING IMPLEMENTATION OF PROCEDURE ES1802.001, SEISMIC RESPONSE PROCEDURE OR

2. TORNADO STRIKING ANYWHERE ON SITE OR

ER 1.1 Page 50 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 18a. (Continued)

3. WIND SPEEDS EXCEEDING 75 MPH FOR GREATER THAN OR EQUAL TO 5 MINUTES.

VAS INDICATORS A POINT MESSAGE A1626 UPPER WIND SPEED (INSTANT), OR A1628 LOWER WIND SPEED (INSTANT)

OR

4. A VERIFILED TIDAL WAVE WARNING FOR THE HAMPTON AND SEABROOK BEACHES. l

ER 1.1 Page 51 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 18a. (Continued)

SEClRITY EVENTS A determination by the Shift Manager or notification by the Security Supervisor that:

[1. AN ARMED INTRUDER(S) IS ATTEMPTING TO ENTER THE PROTECTED AREA ,

OR

2. A SABOTAGE ACT HAS OCCURRED (OR,BEEN ATTEMPTED) INSIDE

2. THE PROTECTED AREA BUT QUTSIDE ANY VITAL AREAS I OR

3. THERE IS A CREDIBLE BOMB THREAT INSIDE THE PROTECTED AREA BUT OUTSIDE ANY VITAL AREAS OR I4. THE SECURITY DEPARTMENT RECEIVES NOTIFICATION OF A CREDI3LE, SITE-SPECIFIC SECURITY THREAT. I OR

5. A LARGE DISTURBANCE OUTSIDE THE PROTECTED AREA THAT COUID RESULT IN A BREACH OF THE PROTECTED AREA FENCE. l

ER 1.1 Page 52 Rev. 35 Figure AMiscellaneous Emergency Conditious and Emergency Action Levels (Continued)

Iitiating Condition for UNUSUAL EVENT 18a. (Continued)

MANMADE EVENTS

1. AN AIRCRAFT CRASH ANYWHERE ON SITE THAT MAY ADVERSELY IMPACT NORMAL STATION OPERATIONS OR

2. AN EXPLOSION ANYWHERE NEAR SlIE OR ON SITE THAT MAY ADVERSELY IMPACT NORMAL STATION OPERATIONS OR

3. A RELEASE OF TOXIC OR FLAMMABLE GAS FROM ANYWHERE NEAR SITE OR ON SITE THAT MAY ADVERSELY IMPACT NORMAL STATION OPERATIONS OR

4. PLANT SHUTDOWN DUE TO TURJINE DAMAGE WITHOUT CASING PENETRATION.

a) A VALID TURBINE TRIP SIGNAL EXISTS AND b) TURBIM BEARING VIBRATION EXCEEDS 15 MILS AND c) EXCESSIVE OR UNUSUAL TURBINE NOISE EXISTS.

DISCRETIONARY EVENTS AN EVENT IS IN PROGRESS OR HAS OCCURRED THAT INDICATES A POTENTLAL DEGRADATION OF THE LEVEL OF SAFETY OF THE STATION.

ER 1.1 Page 53 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 18b. Hazards experienced or projected which involve substantial degradation of station -safety.

EMERGENCY ACTION LEVELS NATURAL PHENOMENA

1. OBE EARTHQUAKE AS INDICATED BY:

a) VAS ALARM D POINT MESSAGE D5452 SEISMIC EVENT IN PROGRESS AND -

b) YELLOW "EVENT" LIGHT LIT AND RED "OBE" LIGHT LIT ON SEISMIC MONITORING CONTROL CABINET 1-SM-CP-58 POWER PANEL c) EITHER'bF THE FOLLOWNd:

(1) THE EARTHQUAKE IS FELT BY STATION PERSONNEL OR ."I

-.;- (2) - AN OBE EARTHQUAK+-OCCURRENCE IS VERIFIED DURING IMPLEMENTATION bOPROCEDIURE ES 1802.001, SEISMIC RESPONSE PROCEDURE .

-. - l ' .'i - ; r;x

r.  : ~~

I . i },,: . ~ .

"4~ "? .iB/4z

2. TORNADO STRKING ANY PERMANENT STRUCTURE INSIDE THE PROTECTED AREA THAT CONTAINS SYSTEMS REQUIRED FOR SAFE SHUTDOWN 'AIi , . , i> - -- , I OR

ER 1.1 Page 54 Rev. 35 Figure I Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT 18b. (Continued)

3. WIND SPEEDS EXCEEDING 85 MPH FOR GREATER THAN OR EQUAL TO 5 MlNUTES.

VAS INDICATORS A POINT MESSAGE A1626 UPPER WIND SPEED (INSTANT), OR A1628 LOWER WIND SPEED (INSTANT)

OR

4. POT'ENTIAL STE FLOODING AS INDICATED BY WATER LEVELl APPROACHING THE TOP OF THE SEA WALL.J MANMADE EVENTS I . AN AIRCRAFT CRASH IMPACTING ON ANY PERMANENT STRUCTURE INSIDE THE PROTECTED AREA THAT CONTAINS SYSTEMS REQUIRED FOR SAFE SHUTDOWN OR

2. AN EXPLOSION OR MISSILE IMPACT DAMAGING ANY PERMANENT STRUCTURE INSIDE THE PROTECTED AREA THAT CONTAINS SYSTEMS

- REQUIRED FOR SAFE SHUTDOWN

3. UNCONTROLLED RELEASE OF SIGNIFICANT QUANTITES OF A TOXIC OR FLAMMABLE GAS ANYWHERE INSIDE OR INTO THE PROTECTED AREA AND

4. THE CONCENTRATION OF THE GAS MAY (OR HAS) ADVERSELY IMPACT(ED) NORMAL STATION OPERATIONS OR l5. TURBINE FAILURE WITH CASING PENETRATION.

DISCRETIONARY EVENTS AN EVENT IS IN PROGRESS OR HAS OCCURRED THAT INVOLVES AN ACTUAL OR POTENTIAL SUBSTANTIAL DEGRADATION OF THE LEVEL OF SAFETY OF THE STATION.

ER 1.1 Page 55 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for ALERT I 8b. (Continued)

SECURITY EVENTS A determination by the Shift Manager or notification by the Security Supervisor that:

AN ARMED INTRUDER(S) HAS GAINED ENTRY INTO THE PROTECTED AREA

2. A SABOTAGE ACT HAS OCCURRED (OR BEEN ATTEMPTED) INSIDE

2. ANY VITAL AREA OR

3. THERE IS A CREDIBLE BOMB TIREAT INSIDE ANY VITAL AREA

- - - 3,ts- I,~ -I .: ... '.  : *,.$

4. A LARGE DISTURBANCE HAS RESULTED 1N OCCUPATION OF ANY PORTION OF THE PROTECTED AkEA.

~~~~~

ER 1.1 Page 56 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition For SITE AREA EMERGENCY 18c. Hazards experienced or projected which involve major failures of station functions needed for public protection.

EMERGENCY ACTION LEVELS NATURAL PHENOMENA SSE EARTHQUAKE AS INDICATED BY:

a) VAS ALARM D POINT MESSAGE 5452 SEISMIC EVENT IN PROGRESS AND b) YELLOW "EVENT' LIGHT LIT AND RED "OBE" LIGHT LIT ON SEISMIC MONITOR CONTROL CABINET 1-SM-CP-58 POWER PANEL AND c) THE EARTHQUAKE IS FELT BY STATION PERSONNEL AND d) SUBSEQUENT ENGINEERING ANALYSIS CONFIRMS THAT THE EARTHQUAKE MET OR EXCEEDED SSE LEVELS.

OR

2. WIND SPEEDS INDICATED AT 100 MPH (OR MORE) FOR GREATER THAN OR EQUAL TO 5 MINUTES VAS INDICATORS A POINT MESSAGE A1626 UPPER W-IND SPEED (INSTANT), OR A1628 LOWER WIND SPEED (INSTANT)

OR

13. SITE FLOODING AS INDICATED BY WATER LEVEL OVER THE SEA WALL.

ER 1.l Page 57 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action tevels (Continued)

Initiating Condition For SITE AREA EMERGENCY 18c. (Continued)

MANMADE EVENTS

1. AN AIRCRAFT CRASH RESULTING IN DAMAGE OR FIRE INSIDE ANY VITAL AREA OR

2. AN EXPLOSION OR MISSILE IMPACT DAMAGING EQUIPMENT INSIDE ANY VITAL AREA

3. UNCONTROLLED RELEASE OFsIGNICANr QUANTMES OF TOXIC OR FLAMMABLE GASSES INSWE OR INTO ANY VITAL AREA.

SECURITYEVN

1. OCCUPATION OF A VITAL AREA BY AN ARMED INTRUDER(S) IS DISCRETIONARY EVENTS AN EVENT IS IN PROGRESS OR HAS CCUR?I},THAT INVOLVES ACTUAL OR LIKELY MAJOR FAILUJRES QF STeTION FUNCTIONS NEEDED FOR PROTECTION OF THE PUBLIC.

ER 1.1 Page 58 Rev. 35 Figure I Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for GENERAL EMERGENCY 18d. Hazards experienced or projected which involve substantial core degradation and/or gross loss of containment integrity.

EMERGENCY ACTION LEVELS NATURAL PHENOMENA/MANMADE EVENTS THERE HAS BEEN OR WILL BE MAJOR INTERNAL OR EXTERNAL EVENTS THAT COULD CAUSE OR HAVE CAUSED MASSIVE COMMON DAMAGE TO PLANT SYSTEMS RESULTING IN ANY OF THE GENERAL EMERGENCY IN1TIATING CONDITONS.

SECURITY THREATS A VITAL AREA HAS BEEN OCCUPIED BY AN ARMED INTRUDER(S).

DISCRETIONARY EVENTS AN EVENT IS IN PROGRESS OR HAS OCCURRED THAT INVOLVES ACTUAL OR IMMINENT SUBSTANTIAL CORE DEGRADATION OR MELTING WITH POTENTIAL FOR LOSS OF CONTAINMENT INTEGRITY.

ER 1.1 Page 59 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for UNUSUAL EVENT 19a. Loss of shutdown cooling with RCS loops filled NOTE This Initiating Condition does not apply in-Modes 1,2, 3, or 4, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

. IRRADIATED FUEL IS PRESENT IN THE REACTOR VESSEL AND

2. RCS IS ALIGNED FOR SHUTDOWN COOLING

-IA,ND.,-A,,i ;A

3. SHU.T.DOWN COOINCG11AS;i it gi. l AND

4. RCS LOOPS ARE FILLED NOTE - REFER TO TECHNICAL CLARFICATION #162 FOR DEFINITION OF RCS LOOPS FILLED.

AND

5. ONE HOUR HAS ELAPSED SINCE SHUTDOWN COOLING WAS LOST OR

6. RCS SUBCOOLING IS LESS THAN 100 F.

ER 1.1 Page 60 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action L,evels (Continued)

Initiating Condition for ALERT 19b. Loss of shutdown cooling with RCS loops not filled NOTE This Initiating Condition does not apply in Modes 1, 2, 3, or 4, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS

1. IRR-ADIATED FUEL S PRESENT IN THE REACTOR VESSEL AND l2. RCS IS ALIGNED FOR SHUTDOWN COOLING l AND

3. SHtUTDOWN COOILING HAS BEEN LOST AND

4. RCS LOOPS ARE NOT FILLED NOTE - REFER TO TECHNICAL CLARIFICATION #162 FOR DEFINITION OF RCS LOOPS FILLED.

AND

5. ONE HOUR HAS ELAPSED SINCE SHUTDOWN COOLING WAS LOST OR

6. RCS TEMPERATURE GREATER THAN 2000 F.

ER 1.1 Page 61 Rev. 35 Figure 1 Miscellaneous Emergency Conditions and Emergency Action Levels (Continued)

Initiating Condition for SITE AREA EMERGENCY 19c. Loss of shutdown cooling without containment integrity NOTE This Initiating Condition does not apply in Modes 1, 2, 3, or 4, or when the reactor vessel is defueled.

EMERGENCY ACTION LEVELS I. IRRADIATED FUEL IS PRESENT IN THE REACTOR VESSEL AND

2. RCS IS ALIGNED FOR SHUTDOWN COOLING.

AND' 3,.- SHUTDOWN COOLING HAS BENILQST-

4. . RCSi.TIERAT1E GREATEETHAI.200°F-,...-

AND

- 4 I6 . -. FO [ ' Jj . .

{]* ( ' ' §' . .a; :

5. RCSISOPENTOAIMOSPHERE AND

6. CONTAINMENT INTEGRITY IS NOT SET.

ER 1.1 Page 62 Rev. 35 Figure 2 Dose Assessment Data Points MPC POINTS/

RDMS CHANNEL # DESCRIPTION UNITS/MEASURE C3000 Time after Shutdown hr/min C0784 Upper Wind Speed mph C0786 Upper Wind Direction (from) deg C0783 Lower Wind Speed mph C0785 Lower Wind Direction (from) deg C0787 Lower Delta Temp El 150/43 F C0788 Upper Delta Temp El 209/43 F C0797 Precipitation in/qtr hr C0798 Solar Radiation Langley/min.

A3778 Contm Encl/Outside Atmos DP (-)In. Nc.

C0726 Contrn Avg Press (Band) psig C1ooo Contm Dose Rate (Have)

AM104 Lo Range Personnel Hatch mr/hr AM105 Hi Range Personnel Hatch mr/hr RM-6528-1, 2 & 3 WRGM Concentration jLCi/cc RM-6528-4 Plant Discharge Rate jiCi/sec RM-6481-1 Main Steam Line Loop 1 mr/hr RM-6482-1 Main Steam Line Loop 2 mr/hr RM-6482-2 Main Steam Line Loop 3 mr/hr RM-6481-2 Main Steam Line Loop 4 mr/hr D5214 ASDV A Open/Closed D5215 ASDV B Open/Closed D5216 ASDV C Open/Closed D5217 ASDV D Open/Closed C3145 SG A Avg Pressure Band psig C3146 SG B Avg Pressure Band psig C3147 SG C Avg Pressure Band psig C3148 SG D Avg Pressure Band psig

i~~~~

ER 1.1 Page 63 Rev. 35 Figure 3 Summary of Changes Rev. 35:

In EAIL 7b, added an initiatingconditionfor an Alert.

In EAL 16a, 16b, and 16c, removed the condition of verification of afireby thte FireBrigade Leader.

In EAL 18a, 18b, 18c and 18d, removed the words descriptivewords 'malicious'and 'ostie' from 'Armed Intruder.' -

Rev. 34: .r. .. ; _

In §3.0 added sentence to precaution 2 to allow the STED or SED to make an emergency classification based on anticipated.events (CR 02-11319).

In §3.0, deleted precaution 5. Renumbered subsequent precautions accordingly.

In §3.0, revised precaution 7 to add that reclassifications made by the SED are deemed to be declared when the SED announces the classification in the Control Room or TSC.

In §3.0, revised precaution 8 to direct implementation of the applicable ER 1.2 STED checklist through to state notification before terminating or reclassifying the event (CR 02-04545).

In §3.0, revised precaution 9 to direct the Shift Manager to notify the ENM for notification of the states where emergency-related indications are received but cleared before an emnergency is declared. -- -

In §3.0, revised precaution 10 to direct the Shift Manager to notify the ENM for notification of the states where it was determined that an emergency classification was warranted by not declared after emergency-related indicatidf&hAd 6keal. "'

In §5.0, added a Note after action 5.1.9 thRit inplementation of ER 1.2 is not required after activation of the TSC,at an Alert or highe emergency classification level.

In Figure 1,initiating condition 18b, EAL 3, changed wind speed value from 90 mph to 85 mph.

In Figure 1, initiating condition 18c, EAL 1, referred to subsequent engineering analysis versus use of procedure ES 1802.001 to confirm that an earthquake.met or exceeded SSE levels.

In Figure 1, initiating condition 18c, EAL 3, changed wind speed from 110 mph to 100 mph.

Moved "using hardwired information" from §5.1, step 2, to §3.0, step 4 (CR 01-00128).