Text

EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
	ML110060222
Person / Time
Site:	Salem, Hope Creek
Issue date:	07/30/2010
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0355 EP-SC-111-200
	Download: ML110060222 (443)
	v • d • e

Attachment 5 SGS EAL Technical Bases Document (Strike-out Version)

SGS ECG -EAL Technical Bases EP-SC-1 11-200.LLC Salem Generating Station Event Classification Guide (ECG)Emergency Action Level Technical Bases Draft E 7/30/2010 SGS ECG -EAL Technical Bases EP-SC-I 11-200 SALEM EVENT CLASSIFICATION GUIDE (ECG)EMERGENCY ACTION LEVEL (EAL) TECHNICAL BASES TABLE OF CONTENTS ECG -EAL Bases Front-Matter Materials:

EP-SC-1 11-200 SGS ECG -EAL Technical Bases Table of Contents EP-SC-1 11-201 Emergency Action Level (EAL) Technical Basis Introduction EP-SC-1 11-202 ECG Usage ECG EAL Sections -Bases Information:

EP-SC-1 11-203 EAL Bases for Category RI -Offsite Rad Conditions EP-SC-1 11-204 EAL Bases for Category R2 -Onsite Rad Conditions

/ Fuel Pool Events EP-SC-1 11-205 EAL Bases for Category R3 -CR/CAS Rad EP-SC-1 11-206 EAL Bases for Category E -ISFSI EP-SC-1 11-207 EAL Bases for Category H1 -Hazards -Natural & Destructive Phenomena (Quake, High Winds / Tornado, Turbine Rotating Component Failure, Internal Flooding, River Level, Vehicle Crash / Projectile Impact)EP-SC-1 11-208 EAL Bases for Category H2 -Hazards -Fire or Explosion EP-SC-1 11-209 EAL Bases for Category H3 -Hazards -Hazardous Gas EP-SC-1 11-210 EAL Bases for Category H4 -Hazards -Security EP-SC-1 11-211 EAL Bases for Category H5 -Hazards -Control Room Evacuation EP-SC-1 11-212 EAL Bases for Category H6 -Hazards -EC Judgment EP-SC-1 11-213 EAL Bases for Category S1 -System Malfunction

-Loss of AC Power Salem Page 1 of 3 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-1 11-200 EP-SC-1 11-214 EP-SC-1 11-215 EP-SC-111-216 EP-SC-1 11-217 EP-SC-1 11-218 EP-SC-1 11-219 EP-SC-1 11-220 EP-SC-1 11-221 EP-SC-111-222 EP-SC-1 11-223 EP-SC-1 11-224 EP-SC-1 11-225 EP-SC-1 11-226 EP-SC-1 11-227 SALEM EVENT CLASSIFICATION GUIDE (ECG)EMERGENCY ACTION LEVEL (EAL) TECHNICAL BASES TABLE OF CONTENTS EAL Bases for Category S2 -System Malfunction

-Loss of DC Power EAL Bases for Category S3 -System Malfunction

-ATWT/Criticality EAL Bases for Category S4 -System Malfunction

-Inability to Reach or Maintain Shutdown Conditions EAL Bases for Category S5 -System Malfunction

-Loss of Annunciators

/Instrumentation EAL Bases for Category S6 -System Malfunction

-Communication EAL Bases for Category S7 -System Malfunction

-Fuel Clad Degradation EAL Bases for Category S8 -System Malfunction

-RCS Leakage EAL Bases for Category F1 -Fission Product Barriers -Fuel EAL Bases for Category F2 -Fission Product Barriers -RCS EAL Bases for Category F3 -Fission Product Barriers -Containment EAL Bases for Category C1 -Cold Shutdown / Refuel System Malfunction

-Loss of AC Power EAL Bases for Category C2 -Cold Shutdown / Refuel System Malfunction

-Loss of DC Power EAL Bases for Category C3 -Cold Shutdown / Refuel System Malfunction

-RPV Level EAL Bases for Category C4 -Cold Shutdown / Refuel System Malfunction

-RCS Temperature Salem Page 2 of 3 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-1 11-200 SALEM EVENT CLASSIFICATION GUIDE (ECG)EMERGENCY ACTION LEVEL (EAL) TECHNICAL BASES TABLE OF CONTENTS EP-SC-1 11-228 EAL Bases for Category C5 -Cold Shutdown / Refuel System Malfunction

-Communication EP-SC-1 11-229 EAL Bases for Category C6 -Cold Shutdown / Refuel System Malfunction

-Inadvertent Criticality ECG -EAL Technical Bases Supporting Documents:

EP-SC-1 11-230 -Use of Fission Product Barrier Table (Tab -Attachment 1)EP-SC-1 11-231 -EAL Bases Figures / Drawings (Tab -Attachment 2)EP-SC-1 11-232 -EAL Definitions (Tab -Attachment 3)EP-SC-1 11-233 -Glossary of Abbreviations

& Acronyms (Tab -Attachment 4)EP-SC-1 11-234 -SGS-to-NEI 99-01 EAL Cross-reference (Tab -Attachment 5)EP-SC-1 11-235 -Salem EAL Rad Set-Point Calculation Document (Tab -Attachment 6)Salem Page 3 of 3 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-1 11-201 Nu clear LLC Salem Generating Station Event Classification Guide (ECG)Emergency Action Level Technical Bases Draft E 7/30/10 SGS ECG -EAL Technical Bases EP-SC-1 11-201 TABLE OF CONTENTS Section Page 1. Purpose .....................................................................................................

2 2. Em ergency Classification Descriptions

.........................................................

2 3. Fission Product Barriers ................................................................................

3 4. EAL Relationship to EO Ps ............................................................................

5 5. Sym ptom -Based vs. Event-Based Approach ...............................................

5 6. EAL O rganization

........................................................................................

6 7. O perating M ode Applicability

.......................................................................

8 8. EAL Technical Bases O rganization

..............................................................

9 9. References

.................................................................................................

11 Salem Page 1 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 1. PURPOSE This document provides an explanation and rationale for each Salem Generating Station (SGS) Emergency Action Level (EAL). It should be used to facilitate review of the SGS EALs, provide historical documentation for future reference and serve as a training aid. Decision-makers responsible for implementation of the Event Classification Guide (ECG) may use this document as a technical reference in support of EAL interpretation.

This information may assist the Emergency Coordinator in making classifications, particularly those involving judgment or multiple events. The information may also be useful in training, for explaining event classifications to offsite officials, and facilitate regulatory review and approval of the classification scheme.The expectation is that emergency classifications are to be made as soon as conditions are present and recognizable for the classification, but within 15 minutes or less in all cases of conditions present. Use of this document for assistance is not intended to delay the emergency classification.

This document is controlled pursuant to 10 CFR 50.54(q).2. Emergency Classification Descriptions The NRC and Federal Emergency Management Agency (FEMA) established four emergency classes for fixed nuclear facilities.

An emergency class is used for grouping off-normal nuclear power plant conditions according to their relative radiological seriousness and the time sensitive onsite and offsite actions needed to respond to such conditions.

The four emergency classes are (in order of less severe to most severe):* Unusual Event (UE)* Alert (A)* Site Area Emergency (SAE)* General Emergency (GE)2.1 Unusual Event Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicates a security threat to facility protection has been initiated.

The lowest level of emergency at the plant, which can usually be handled by the normal operating shift.Salem Page 2 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201* No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Dose consequences in Unrestricted Areas would not reach 20 mRem TEDE.2.2 Alert Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION.* Emergency Response personnel are required in addition to the normal operating shift.The entire emergency response organization is called in. The TSC is activated, and the EOF and ENC are manned and may activate if needed for support.* Any release of radioactive material is expected to be limited to a small fraction of the EPA Protective Action Guideline exposure levels. Dose consequences in Unrestricted Areas would not reach 100 mRem TEDE.2.3 Site Area Emergency Events are in progress or have occurred which involve an actual or likely failure of plant functions needed for protection of the public or HOSTILE ACTION that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public." The entire emergency response organization is activated.

Any release of radioactive material is not expected to exceed EPA Protective Action Guideline exposure levels beyond the plant boundary.

Dose consequences in Unrestricted Areas not to exceed 1000 mRem TEDE.2.4 General Emergency Events are in process or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTIONS that result in an actual loss of physical control of the facility." The entire emergency response organization is activated." Release of radioactive material can be expected to exceed EPA Protective Action Guideline exposure levels of 1000 mRem TEDE in Unrestricted Areas.3. Fission Product Barriers Many of the EALs derived from the NEI 99-01 methodology are fission product barrier based.That is, the conditions that define the EALs pertain to the loss or potential loss of one or more Salem Page 3 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 of the three fission product barriers. "Loss" and "Potential Loss" signify the relative damage and threat of damage to the barrier. "Loss" means the barrier no longer assures containment of radioactive materials; "Potential Loss" infers an increased probability of barrier loss and decreased certainty of maintaining the barrier.3.1 Barrier Descriptions The EAL fission product barriers are: Fuel Clad Barrier (FB): The Fuel Clad barrier consists of the zircalloy or stainless steel fuel bundle tubes that contain the fuel pellets.Reactor Coolant System Barrier (RB): The Reactor Coolant System barrier includes the Reactor Coolant System primary side and its connections up to and including the pressurizer safety and relief valves, and other connections up to and including the primary isolation valves.Containment (CB): The Containment barrier includes the containment building and connections up to and including the outermost containment isolation valves. This barrier also includes the main steam, feedwater, and blowdown line extensions outside the containment building up to and including the outermost secondary side isolation valve.3.2 Emergency Classification Based on Fission Product Barrier Degradation The following criteria for event classification relate to fission product barrier loss or potential loss: UNUSUAL EVENT ANY loss or ANY potential loss of Containment ALERT ANY loss or ANY potential loss of either Fuel Clad or RCS SITE AREA EMERGENCY Loss or potential loss of ANY two barriers OR Potential loss of 2 barriers with the loss of the 3 rd barrier GENERAL EMERGENCY Loss of ANY two barriers and loss or potential loss of third barrier Salem Page 4 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-111-201 Discrete threshold values associated with fission product barrier loss and potential loss are given in Attachment 1, Use of Fission Product Barrier Table. The bases for the thresholds are discussed in the following ECG sections:* EP-SC-1 11-221 EAL Bases for Fuel Clad Barrier* EP-SC-1 11-222 EAL Bases for RCS Barrier" EP-SC-1 11-223 EAL Bases for Containment Barrier A point system (described in Attachment

1) is used to determine fission product barrier emergency classification levels as well as Protective Action Recommendations (PARs) if a General Emergency is declared.4. EAL Relationship to EOPs Where possible, the EALs have been made consistent with and utilize the conditions defined in the SGS Emergency Operating Procedures (EOPs). While the symptoms that drive operator actions specified in the EOPs are not indicative of all possible conditions which warrant emergency classification, they define the symptoms, independent of initiating events, for which reactor plant safety and/or fission product barrier integrity are threatened.

When these symptoms are clearly representative of one of the NEI Initiating Conditions, they have been utilized as an EAL. This permits rapid classification of emergency situations based on plant conditions without the need for additional evaluation or event diagnosis.

Although some of the EALs presented here are based on conditions defined in the EOPs, classification of emergencies using these EALs is not dependent upon EOP entry or execution.

The EALs can be utilized independently or in conjunction with the EOPs.5. Symptom-Based vs. Event-Based Approach To the extent possible, the EALs are symptom-based; that is, the action level threshold is defined by values of key plant operating parameters that identify emergency or potential emergency conditions.

This approach is appropriate because it allows the full scope of variations in the types of events to be classified as emergencies.

However, a purely symptom-based approach is not sufficient to address all events for which emergency classification is appropriate.

Particular events to which no predetermined symptoms can be ascribed have also been utilized as EALs since they may be indicative of potentially more serious conditions not yet fully realized.Salem Page 5 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-11 11 -201 6. EAL Organization 6.1 EAL Groups The EAL scheme is divided into three broad groups: " EALs applicable under all plant operating modes -This group would be reviewed by the EAL-user any time emergency classification is considered." EALs applicable only under hot operating modes -This group would only be reviewed by the EAL-user when the plant is in Hot Shutdown, Hot Standby, Startup or Power Operations operating modes." EALs applicable only under cold operating modes -This group would only be reviewed by the EAL-user when the plant is in Cold Shutdown or Refueling operating modes or when the Reactor Vessel is defueled.The purpose of the groups is to avoid review of hot condition EALs when the plant is in a cold condition and avoid review of cold condition EALs when the plant is in a hot condition.

This approach significantly minimizes the total number of EALs that must be reviewed by the EAL-user for a given plant condition, reduces EAL-user reading burden and, thereby, speeds identification of the EAL that applies to the emergency.

6.2 EAL Categories and Subcategories Within each EAL group, EALs are assigned to categories/subcategories.

Category titles generally align with the EAL Recognition Categories of NEI 99-01.Subcategory titles are selected to represent conditions that are operationally significant to the EAL-user.

Subcategories are used as necessary to further divide the EALs of a category into logical sets of possible emergency classification thresholds.

Salem Page 6 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 The SGS EAL categories/subcategories and their relationship to NEI Recognition Categories are listed below.SGS EALs Category T Subcategory Group: Any Operating Mode: R -Abnormal Rad Release / Rad Effluent 1 -Offsite Rad Conditions 2 -Onsite Rad Conditions/Fuel Pool Events 3 -CR/CAS Rad E -ISFSI Spent Fuel Transit H -Hazards & Other Conditions Affecting 1 -Natural & Destructive Phenomena Plant Safety 2 -Fire or Explosion 3 -Hazardous Gas 4 -Security 5 -Control Room Evacuation 6 -EC Judgment Group: Hot Conditions:

S -System Malfunction 1 -Loss of AC Power 2 -Loss of DC Power 3 -ATWT / Criticality 4 -Inability to Reach or Maintain Shutdown Conditions 5 -Instrumentation 6 -Communications 7 -Fuel Clad Degradation 8 -RCS Leakage F -Fission Product Barrier Degradation None Group: Cold Conditions:

C -Cold Shutdown / Refuel System 1 -Loss of AC Power Malfunction 2 -Loss of DC Power 3 -RCS Level 4 -RCS Temperature 5 -Communications 6 -Inadvertent Criticality Salem Page 7 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 7. Operating Mode Applicability With the exception of ISFSI (which is not assigned an operating mode), NEI 99-01 assigns one or more operating modes to each EAL. The ISFSI EAL will be applicable in all operating modes at Salem Generating Station; as such, operating mode applicability is N/A for the ISFSI EAL.7.1 Operating Mode Definitions THERMAL MODE K eff POWER* TAVG 1. Power Operation

> 0.99 > 5% > 350 F 2. Startup > 0.99 < 5% > 350 F 3. Hot Standby < 0.99 0 > 350 F 4. Hot Shutdown < 0.99 0 > 200'F & < 350'F 5. Cold Shutdown < 0.99 0 -< 200 F 6. Refueling

- <0.95 0 5 140 F Defueled NA NA NA -no fuel in Reactor Vessel* Excluding Decay Heat** Fuel in the Reactor Vessel with the head closure bolts less than fully tensioned or with the head removed 7.3 Applicability The plant operating mode that exists at the time that the event occurs (prior to any protective system or operator action is initiated in response to the condition) should be compared to the operating mode applicability of the EALs. If a lower or higher plant operating mode is reached before the emergency classification is made, the declaration shall be based on the operating mode that existed at the time the event occurred.For events that occur in Cold Shutdown or Refueling, escalation is via EALs that have Cold Shutdown or Refueling for mode applicability, even if Hot Shutdown (or a higher mode) is entered during any subsequent heat-up. In particular, the fission product barrier EALs are applicable only to events that initiate in Hot Shutdown or higher.Salem Page 8 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 8. EAL Technical Bases Organization EAL technical bases are provided for each EAL according to:* EAL category (R, E, H, S, F and C)* EAL subcategory Figures cited in EAL basis discussions are provided in Attachment

2. EAL defined terms and abbreviations and acronyms are listed in Attachments 3 and 4, respectively.

For each EAL, the following information is provided:* EAL Category Letter & Title* EAL Subcategory Number & Title* Initiating Condition Site-specific description of the generic IC given in NEI 99-01.* Operating Mode Applicability One or more of the following operating modes comprise the conditions to which each EAL is applicable:

1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown, 5 -Cold Shutdown, 6 -Refueling, D -Defueled, N/A -Not Applicable or All.For Fission Product Barrier Table bases, Operating Mode Applicability is always Operating Modes 1, 2, 3 and 4. For these EALs, the barrier threat (Loss or Potential Loss) is listed.* EAL# and Classification Level (EAL# & Point Value for Fission Product Barrier Table EAL bases): The EAL number is a unique identifier to support accurate communication of the emergency classification to onsite and offsite personnel.

Four characters define each EAL identifier:

Category R, E, H, C and S EALs: (Example:

SU7.1)1. First character (letter) -Corresponds to the EAL category (R, E, H, C or S)2. Second character (letter) -Emergency classification level: U for Unusual Event, A for Alert, S for Site Area Emergency, or G for General Emergency.

3. Third character (number):

Subcategory number within the given category.Subcategories are ýequentially numbered beginning with the number one (1).Salem Page 9 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-201 If a category does not have a subcategory, this character is assigned the number one (1).4. Fourth character (number):

The numerical sequence of the EAL within the EAL subcategory.

If the subcategory has only one EAL, it is given the number one (1).Selected EALs in Category H have been designated as "Common Site" events.These events are annotated with the phrase "(Common Site)" immediately following the classification level.Category F Fission Product Barrier EALs: (Example CB4-P)1. First and second characters (letters) identify the barrier to which the EAL applies.FB: Fuel Clad Barrier RB: Reactor Coolant Barrier CB: Containment Barrier 2. Third character (number) -Sequential number beginning with the number one (1) for the first threshold in the barrier loss or potential loss of the Fission Product Barrier Table (Attachment 1)3. Last character (letter) preceded by a dash (-) designates if EAL is for a potential loss or loss of the barrier in question.P: Potential Loss L: Loss" EAL (enclosed in rectangle)

Exact wording of the EAL as it appears in the EAL wallcharts.

Basis The basis discussion applicable to the EAL taken from NEI 99-01.Salem Page 10 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases E P-SC- 111 -201" Explanation/Discussion/Definitions Description of the site-specific rationale for the EAL." EAL Basis Reference(s)

Source documentation from which the EAL is derived. The first reference in each list gives the NEI 99-01 IC and example EAL number. A cross-reference of SGS EALs and NEI 99-01 ICs/EALs is given in Attachment

5.9. REFERENCES

9.1 NEI 99-01 Revision 5, Methodology for Development of Emergency Action Levels, Final, February 2008 (ADAMS Accession Number of ML080450149) 9.2 NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels Revision 4, Dated January 2003 (December 12, 2005) (ADAMS Accession Number of ML051450482) 9.3 NRC Regulatory Issue Summary (RIS) 2007-02 Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events, Dated February 2007 (ADAMS Accession Number of ML06237031 1)9.4 Salem EAL Comparison Matrix -NRC submittal document that defines differences between NEI 99-01, Rev. 05 and PSEG submitted Salem EALs Salem Page 11 of 11 Rev. 0 (draft E)Introduction SGS ECG -EAL Technical Bases EP-SC-1 11-202 EVENT CLASSIFICATION GUIDE (ECG) USE NOTE It is expected the Shift Manager (SM) always serves at the Emergency Coordinator (EC) during the initiating event even if the SM is out of the control room. The Control Room Supervisor (CRS) assumes operational command and control responsibility for the shift crew but not as the EC. The CRS should ensure that the SM is immediately called back to the control room on any conditions that require ECG assessment.

Only if the SM is not able (sick or hurt) may the CRS serve as the EC.1. EC Judgment The EALs described in the ECG are not all inclusive and will not identify each and every condition, parameter or event which could lead to an event classification.

The following guidance should be used by the EC: IF an EAL has been exceeded, but satisfaction of the Initiating Condition (IC) is in question, THEN CLASSIFY the event lAW the EAL.IF however, it is clear that the EAL has NOT been exceeded (and will not), THEN DO NOT classify the event.IF an IC has been satisfied, but exceeding the specific EAL is in question, THEN CLASSIFY the event lAW the IC.In any case, IF the plant conditions are equivalent to one of the four emergency classes as described in Section 2 of EP-SC-1 11-201, THEN CLASSIFY the event based on EC discretion lAW EALs in Category H.2. Assessment Time 2.1 Timeliness Assessment of an Emergency Condition should be completed in a timely manner, which is considered to be within 15 minutes of when events are known or should have been known.If an EAL specifies a duration time (e.g., loss of annunciators for 15 minutes or longer), the assessment time runs concurrently with the EAL duration time and is the same length.Salem Page 1 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 2.2 Duration Time Exceeded If an event is recognized or reported and the required duration time is known to have already been exceeded, the duration portion of the EAL should be considered as being satisfied and the assessment time for the remaining portions of the EAL should be within 15 minutes from the time of recognition.

3. Implementing Actions The ECG is not a stand-alone document.

At times, the ECG will refer the user to other attachments or procedures for accomplishment of specific evolutions such as: Accountability, Recovery, development of PARs, etc.The ECG should be considered an "Implementing Procedure" and used in accordance with the requirements of a Level 2 -Reference Use procedure as defined in HU-AA-104-101, Procedure Use and Adherence.

The ECG classification sections allow for judgment and decision making as to whether or not an EAL is exceeded.NOTE Comparison of redundant instrumentation, indications, and/or alarms should be used to confirm actual plant conditions.

4. Classification The primary tools for determining the emergency classification level are the EAL wallcharts.

The user of the EAL wallcharts may (but is not required to) consult the EAL Technical Bases in order to obtain additional information concerning the EALs under classification consideration.

To use the EAL wallcharts, follow this sequence: 1. Assess the event and/or plant conditions and determine which EAL Group is most appropriate.

2. Review EAL categories and subcategories on the appropriate wallcharts.

3. For each applicable subcategory, review EALs in the subcategory beginning with the highest emergency classification level to the lowest classification level (left to right).4. If the HOT conditions wallchart is employed, also review the Fission Product Barrier (FPB) Table (Wallchart sheet 3) as follows: a. Examine the FPB categories in the left column of the table.b. Select the category that most likely coincides with event conditions.

c. Review all thresholds in this category for each fission product barrier.d. For each threshold that is exceeded, identify its point value and determine the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Basis, Attachment 1).Salem Page 2 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 NOTE The Emergency Coordinator should classify and declare an emergency before an Emergency Action Level (EAL) is exceeded if, in the EC's judgment, it is determined that the EAL will be exceeded within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5, REVIEW the associated EALs as compared to the event and SELECT the highest appropriate emergency.

If identification of an EAL is questionable refer to paragraph 1 above.If there is any doubt with regard to assessment of a particular EAL, the ECG EAL Technical Basis Document should be reviewed.

Words contained in an EAL that appear in uppercase and bold print (e.g., VALID) are defined at the end of the basis for the EAL. Words or numbers contained in an EAL that are in bold print but not uppercase are EAL threshold values (e.g., _ 15 minutes).6, If an EAL has been exceeded, equal level EALs or lower level EALs are not required to be seperately reported as long as the applicable information is communicated to the NRC using ECG Attachment 5, EP-SC-1 11-F5, NRC Data Sheet Completion Reference.

7, When the Shift Manager (SM) is the Emergency Coordinator, the Shift Technical Advisor (STA) is responsible to perform an independent verification of the EAL classification.

The STA verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO, the Independent Assessor.8, Identify and implement the referenced ECG form based on the Emergency Classification Level." Unusual Event Implement EC-SC-1 11-F1* Alert Implement EC-SC-1 11-F2* Site Area Emergency Implement EC-SC-1 11-F3* General Emergency Implement EC-SC-1 1 1-F4* Unusual Event (Common Site) Implement EC-SC-1 11 -F8 9, Continue assessment after classification and attachment initiation, by returning to the EAL wallcharts to review EALs that may result in escalation/de-escalation of the emergency level.Salem Page 3 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 5. Emergency Short Duration Events 1. A Short Duration emergency event is a transitory event that meets or exceeds one or more EALs for less than 15 minutes (i.e., action is taken and the plant returned to a condition in which no EAL applies).

For a Short Duration event the Control Room Staff is aware of the event and realizes that an EAL had been exceeded.2. Short Duration events that occur will be assessed and emergency classification made, if appropriate, within 15 minutes of control room indications or the receipt of the information, indicating that an EAL has or had been exceeded.

This classification is to be made even if no EALs are currently being exceeded (i.e., actions have been taken to stabilize the Plant such that no EALs currently apply).3. For some events, the condition may be corrected before a declaration has been made.The key consideration in this situation is to determine whether or not further plant damage occurred while the corrective actions were being taken. In some situations, this can be readily determined, in other situations, further analyses (e.g., coolant radiochemistry sampling, may be necessary).

Classify the event as indicated and terminate the emergency once assessment shows that there were no consequences from the event and other termination criteria are met.4. Guidance for classifying transient events addresses the period of time of event recognition and classification (15 minutes).

However, in cases when EAL declaration criteria may be met momentarily during the normal expected response of the plant, declaration requirements should not be considered to be met when the conditions are a part of the designed plant response, or result from appropriate Operator actions.6. Conditions Discovered After-the-Fact There may be cases in which a plant condition that exceeded an EAL was not recognized at the time of occurrence but is identified well after the condition has occurred (e.g., as a result of routine log or record review), and the condition no longer exists. In these cases, an emergency should not be declared.

Reporting requirements of 10 CFR 50.72 are applicable and the guidance of NUREG-1022, Rev. 2, Section 3, should be applied.1. An After-the-Fact event is defined as an event that exceeded an EAL threshold and was not recognized at the time of occurrence but is identified greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the condition has occurred (e.g., as a result of a routine log review, record review, post trip review, engineering evaluation) and the condition no longer exists.2. For an After-the-Fact event the Control Room Staff was either not aware of the event or did not realize that an EAL was exceeded at the time of the occurrence.

3. Plant emergency events that are in progress or have occurred with ongoing adverse consequences/effects should not be considered After-the-Fact events and should therefore be classified and declared as an ongoing emergency event.Salem Page 4 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 4. EMERGENCY CONDITIONS

-After-the-Fact events that occur will be assessed and evaluated to ensure that no EAL currently applies. An emergency declaration is NOT required and a non-emergency, One-Hour Report should be initiated in accordance with non-emergency RALs in the ECG.7. NRC Communications During An Emergency Guidance 1. Complete and accurate communications with the NRC Operations Center during emergencies is required and expected.

The purpose of notifying the NRC within one-hour of an emergency, is to provide event information when immediate NRC action may be required to protect the public health and safety OR when the NRC needs accurate and timely information to respond to heightened public concern. If the information we provide is not accurate or does not contain sufficient detail, then we hamper the NRC from doing their job.2. The NRC Data Sheet, along with the Initial Contact Message Form, is the primary vehicle to ensure the NRC is kept informed.

General Guidance on completing the event description portion of the NRC Data Sheet is provided in the NRC Data Sheet (ECG Attachment 5).8. Event Retraction Guidance IF an ENS notification to the NRC was made as directed by the applicable ECG Attachment AND it is later determined that the event or condition is not reportable, THEN the notification may be retracted as follows: 1. OBTAIN both the Operations Shift Manager's and Shift Manager's approval of any proposed retractions.

Ensure Reg Assurance is consulted prior to approval to retract an Event.2. COMPLETE "page 1" of ECG Attachment, EP-SC-1 11 -F5, NRC Datasheet Completion Reference, providing a retraction of the original notification.

Event Description Section of NRC Data Sheet should explain the rationale for the retraction.

3. NOTIFY the NRC Operations Center and NRC Resident Inspector.

4. RECORD on the "NRC Data Sheet" the name of the NRC contact that received the retraction information.

5. FORWARD the retraction "NRC Data Sheet" with the rest of the original attachment of the ECG that was implemented when the original notification was made to the Operations Shift Manager.Salem Page 5 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 9. Common Site Events Guidance 1. Selected EALs in Category H (Unusual Event level only) have been designated as"Common Site" events. These events will be annotated with the words "Common Site" just below the mode applicability line in the wallcharts and next to the classification level in the EAL Bases document.2. The Common Site UE ECG Attachment 8, EP-SC-1 11-F8, Declaration of "Common Site" UE, will direct the SM to establish agreement on which SM will declare and report the event. Therefore, either Salem or Hope Creek will report Common Site Unusual Events, but not both.3. Events classified at an Alert or higher level require plant specific information to be provided to the states of New Jersey and Delaware, the NRC, and to PSEG Emergency Response Facilities and therefore will not be classified as common site events.10. EAL Classification Considerations

1. Planned evolutions involve preplanning to address the limitations imposed by the condition, the performance of required surveillance testing, and the implementation of specific controls prior to knowingly entering the condition in accordance with the specific requirements of the SGS Technical Specifications.

Activities which cause the site to operate beyond that allowed by the SGS Technical Specifications, planned or unplanned, may result in an EAL threshold being met or exceeded.

Planned evolutions to test, manipulate, repair, perform maintenance or modifications to systems and equipment that result in an EAL value being met or exceeded are not subject to classification and activation requirements as long as the evolution proceeds as planned and is within the operational limitations imposed by the specific operating license. However, these conditions may be subject to the reporting requirements of 10 CFR 50.72.2. All classifications are to be based upon VALID indications, reports or conditions.

Indications, reports or conditions are considered VALID when they are verified by (1)an instrument channel check, or (2) indications on related or redundant indications, or (3) by direct observation by plant personnel, such that doubt related to the indication's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.

3. Although the majority of the EALs provide very specific thresholds, the Emergency Coordinator must remain alert to events or conditions that lead to the conclusion that exceeding the EAL is IMMINENT.

If, in the judgment of the Emergency Coordinator, an IMMINENT situation is at hand, the classification should be made as if the threshold has been exceeded.

While this is particularly prudent at the higher emergency classification levels (as the early classification may provide for more effective implementation of protective measures), it is nonetheless applicable to all emergency classification levels.Salem Page 6 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 4. When multiple simultaneous events occur, the emergency classification level is based on the highest EAL reached. For example, two Alerts remain in the Alert category.

Or, an Alert and a Site Area Emergency is a Site Area Emergency.

Further guidance is provided in RIS 2007-02, Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events.5. Another important aspect of usable EAL guidance is the consideration of what to do when the risk posed by an emergency is clearly decreasing.

A combination approach involving recovery from General Emergencies and some Site Area Emergencies and termination from Unusual Events, Alerts, and certain Site Area Emergencies causing no long term plant damage appears to be the best choice. Downgrading to lower emergency classification levels adds notifications but may have merit under certain circumstances.

Refer to procedure NC.EP-EP.ZZ-0405, Emergency Termination

-Reduction

-Recovery, for detailed directions.

6. The logic used for the Fission Product Barrier EALs reflects the following considerations:

The Fuel Clad Barrier and the RCS Barrier are weighted more heavily than the Primary Containment Barrier. Unusual Events associated with RCS and Fuel Clad Barriers are addressed under EALs in Category S, System Malfunctions.

The ability to escalate to higher emergency classification levels as an event deteriorates must be maintained.

For example, RCS leakage steadily increasing would represent an increasing risk to public health and safety." The Primary Containment Barrier should not be declared lost or potentially lost based on exceeding Technical Specification action statement criteria, unless there is an event in progress requiring mitigation by the Primary Containment barrier. When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS barrier) the Primary Containment Barrier status is addressed by Technical Specifications.

7. Since Salem is a multi-unit station with shared safety-related system and functions, emergency classification level upgrading must also consider the effects of a loss of a common system on more than one unit (e.g., potential for radioactive release from more than one core). For example, the control panels for both units in close proximity within the same room. Thus, Control Room evacuation most likely would affect both units. There are a number of other systems and functions which may be shared. This must be considered in the emergency classification level declaration.

8. SGS and HCGS share a common ISFSI. Classification of events related to spent fuel stored at the ISFSI appear only in the HCGS EAL scheme. Classification of events related to the transfer of spent fuel from SGS to the ISFSI are addressed in the SGS EAL scheme (EAL EU1.1).Salem Page 7 of 8 Rev. 0 (draft E)Usage SGS ECG -EAL Technical Bases EP-SC-1 11-202 This page intentionally blank Salem Page 8 of 8 Rev. 0 (draft E)Usage EALs for: Abnormal Radiological Levels&ISFSI SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 2 times the ODCM for 60 minutes or longer All EAL# & Classification Level: RUI.1 -UNUSUAL EVENT EAL: VALID gaseous monitor reading > Table R-1 column "UE" AND> 60 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Salem Page 1 of 6 Rev. 0 (draft E)EAL#: RU1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent 1 R41 D + 2R41 D o Effluent Noble OR 8.48E+09 pCi/sec 8.48E+08 pCilsec 4.84E+07 pCi/sec 4.84E+05 pCi/sec u Gas SPDS combined (D Unit 1 + Unit 2 release rate Containment Fan Coil 1 (2)R13A/B

---.---- 1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U1= 5.50E+05 cpm Radwaste N/A Disposal See EAL RA1.3.Process 2R18 U2= 9.90E+05 cpm-J Steam 1R19A-D U1= 6.40E+05 cpm U1= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 ---- 3.60E+05 cpm 3.60E+03 cpm Waste* For high radiation conditions on Letdown Line Monitor 1 R31A (2R31), refer to EAL SU7.1 Basis:[Refer- to Appendix A fer a d.taied basis of the rad,-logical l efflu- nt Q/4EALs,]_rk r: r1l; + rf4; + k 1A n + ;+ +H +k'n ii k! +0 In e ,psod, but should delare the event as soon as it is that the condition will likely exeed the applicable time.7 This IGEAL addresses a potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[These controls are loate, in the Off-site D-ose Calculation Manual (ODCM,), and for plants that have not im7plmente Generc Leter- 80 01, in the Radiological Effluent Technical Specifications (RET5 TS.]The occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.Some sites m.ay find it advantageous to addFes re, nn, -4 1I,',;- -4t - Cn.n~.i~ A I -i 1 tftoe) crittf M." C1Vt-jC1fCrtV

=1=071 0 ........ ........ --/-----------------------------------------

The threshold values that equates to a R-ETS-multiple of two times the ODCM limits are-is specified in A4U1-EAL RU 1.1 and ci-,! -A, only to distinguish between non-emergency conditions, and from each other. While these-this multiples obviously corresponds to an off-site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.Salem Page 2 of 6 Rev. 0 (draft E)EAL#: RUI .1 SGS ECG -EAL Technical Bases EP-SC-1 11-203[ReALeases should pot be prerlated or- averwaget.

Fr reamPe, alse effuen raditg 4ox mDoM for 30 minutes does pot meet the threshold.]

This EAL includes anY release forF Which a radioactivity diScharge permnit was not prcpared, or a relcase that exceeds the conditions (e.g., min.imHumI dilutionR flow, maximumn discharge flow, alarm Sctp pints, etc.) On thc applicable pe~rmit.This EAL addresses radioactivity releases, that for whatever reason, cause effluent radiation monitor readings to exceed the threshold identified in the IG"EAL.This EAL is intended for sites that have established effluent monitoring on non-routine release pathways for which a discharge permit would not normally be prepared.Salem Page 3 of 6 Rev. 0 (draft E)EAL#: RU1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203[The ODCM4 establishes a methodology for: determining effluent r-adiation monitorF so tpoints. The QD CM SpecifieS default sourcGe term4s andL, for gaseous releases, pr-esc-ribes-P the os f pr- dteFnod annua! av meneteor-ology in MosF19t .A~itia~ downwin4d 6G this methodology.]

EAL F2 This EAL addresses radioactivity releases, that for whatever reason, cause effluont radiation monitor readings to cxcccd the threshold identified in the IC establishcd by the radioactivity discharge permit. This value may be associated With a planncd batch releash loo a continuous release path.[in either case, the value is estabishd dby the ODM to ofarelease that is no' tin compliance with the RET-S. Indexing the EAL to the C DCM sotpoints in th;' is mann r in sures that the &AL Mi4ln etor be less than the sctpe4# ntabhiedby a specifi e dischar-go p orm:pt.]EAL --3 This EAL addresses uncontrolled releases that are detected by sample analyses, particularly onR unmni~tored pathways, e.g., spills of radio~active liquids into storpm drains' heat exchanger leakage in river water systems, etc-.EAls #4 and #5 The 0. 10 mR'hr value in EAL #4, and the site specific value for EAL #5,is based oe release rate nRot exeeding 500 rcrrm per year.[As provded in the CDhc / RETS, pFrorated over 8766 hours0.101 days 2.435 hours 0.0145 weeks 0.00334 months , multiplied by two, an ro.unded..

(500 ... 8766 .. 2 -0.11 EAL #1 aRd #2 direGtly corrrelate with the IC annual average meteorology i;s required to be used in showing compliance w..ith the ODCM and is used in the alarm Setpoints.

E:ALs ad aFra fuRntion of meteorology, which will like"' be different from the limiting annual average value. Thus, there will likely be a numerical The underlyiRg basis of this EAL involves the degradatonR in the level of safety oft plant implied by the unconRtrolled release. Exceeding EAL #4 or #5 is an indicationp of -An unrcntrolled release.Explanation/Discussion/Definitions:

The column "UE" gaseous release value in Table R-1 (Unit 1 + Unit 2) represents two times the associated effluent monitor alarm setpoint.

This setpoint is set to preclude exceeding the ODCM release rate limits associated with the specified monitor.Salem Page 4 of 6 Rev. 0 (draft E)EAL#: RUI .1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 The plant vent monitors (R41) sample and detect noble gases and collect samples of particulates and iodine discharge through the plant vent. Channel D (R41 D) provides the gaseous effluent release rate (pCi/sec) by combining (product of) the on-range R41A through R41 C with plant vent flow (cc/sec).Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AGI Example EAL #1 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. FSAR Section 11.4 Radiological Monitoring

4. PSBP 315733(4)

Radiation Monitoring System Control Manual Salem Page 5 of 6 Rev. 0 (draft E)EAL#: RU 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 6 of 6 Rev. 0 (draft E)EAL#: RU1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

EAL# & Classification Level: Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 2 times the ODCM for 60 minutes or longer RUI.2 -UNUSUAL EVENT All EAL: ANY VALID liquid monitor reading > Table R-1 column "UE" AND>_ 60 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Salem Page 1 of 6 Rev. 0 (draft E)EAL#: RU 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent 1R41D +2R41D o Effluent Noble OR o Efun NobleneR 8.48E+09 pCi/sec 8.48E+08 pCi/sec 4.84E+07 pCi/sec 4.84E+05 pCi/sec in Gas cmie M ~~~SPDS cmie CD Unit 1 + Unit 2 release rate Containment Fan Coil 1(2)R13A/B

1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U1= 5.50E+05 cpm Radwaste N/A Disposal See EAL RA1.3" Process 2R18 U2= 9.90E+05 cpm-J Steam 1R19A-D U1= 6.40E+05 cpm U1= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 ---- 3.60E+05 cpm 3.60E+03 cpm Waste* For high radiation conditions on Letdown Line Monitor 1 R31A (2R31), refer to EAL SU7.1 Basis:..fu ....! t .! t. .y ...... %Z;.. UU. UI!! diut b juuu I I. 1.jut VV... .Il. U. L L.. .t;. 1; U l m; L t; j jd elapsed, but should declare the Gevet as soon as it is determinod that the ConRdition will likcl This IGEAL addresses a potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[These Gontrol, are loated in the Off Site DoSe CaIGla tiOn M~anual (ODCM), and for plants that h4ave not impplem~et Con er4G Letter- 99-01, in the Radiological Effluent Tcch nical Spec-ifications (RETS,).]

The occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.[Some sites may find it advantageous to addres, gaseous and liquid releases with separate EALs.]The threshold values that equate to a RETS-multiple of two times the ODCM limits are sare specified in AU-I-EAL RU1.2 and AM, R',1 only to distinguish between non-emergency conditions, and from each other. While these-this multiples obviously corresponds to an off-site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.fQPIPfP "ht-n!da nnt hp~ Pnrrw~t~d nt: Pprpoa F=Ar PYP3I p iyryadri~o 4w QODC,- for- 30 mnutes does not moe tth, threshod.

1.pi -, Salem Page 2 of 6 Rev. 0 (draft E)EAL#:RU1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This EAL includes any release for which a diSharge permit was net prepared, or a relcase that eXcoedS the conRditionS (e.g.1, miiu0 dlto flow, aiu diSchage eflew, a arm setpoints, etc.) en the applicable permit.EAL4#This EAL addresses radioactivity releases, that for whatever reason, cause effluent radiation monitor readings to exceed the threshold identified in the 4GEAL.This EAL is intended for sites that have established effluent monitoring on non-routine liquid release pathways for which a discharge permit would not normally be prepared (Containment Fan Coil, SG Blowdown & Chemical Waste Basin) as well as planned batch releases for which a radioactivity discharqe permit is prepared (Liquid Radwaste Disposal).

Salem Page 3 of 6 Rev. 0 (draft E)EAL#: RUI .2 SGS ECG -EAL Technical Bases EP-SC-1 11-203[The ODCM4 establgehes a methodology 9fo determ4inig

'efflu ent radiation monitor: so tpoints. The CDGCM specifie&

defaUlt sourC-e terms and-, for- gaseous releases, pro scr4bes th-e use of proe do ;gmndpq 'a!na average meteorology in the most limiting downwind sector fo showing compliance wit the roegulatOPy comm4itmonts.

This EAL should be determined usinpg this methodology]

EA~L-#2-This EAL addresses radioactiVity releases, that for whatever reason, cause cifluent radiation rcadinng to exceed the threshold identified in the IC established by the radioactivity discharge permit. This value may be associated with a planned batch release,--of a cntEinutous release path.[in , ase, the value is estabhs^hed by the ODM to warn of a release that is no tin com3pliance wi4th the RETS. Indexing the EAL to the ODCM setpeints in this m4annerfi nSUres thtte EFA4L will never be less than the setpoint estabshe '~~by a' SpX ~dic.~ ge prpirm.f EAL#-3 This EAL addresses uncontroelled releases that are detected by sample analyses, particul4arly on unmonitored pathways, e.g., spills of radioactive liquids into storm drains, heat exchanger leakage in river water systems, etc.EAI os # and #5 The 0.10 mRhr value in EAL #4, and the Site specific value for EAL #5,is based ona a releasc rate not exeedinRg 500 mrem per year.[As providedl in the ODCM / RET-S, pror~ated over 87-66 hours8, m~ultipfied by two, an rounded. (500 .- 8766 x 2 -0.11! .]EAL #1 and #2 directly coFrrelate with the I since a"nnual average meteorology required to be used in showing complianRe with the -DCM and is used iR calcUlating the alarm setpoints.

E=ALs #4 and #5 arc a functionR of actual meteorology, which Will likely be different from the limiting annual average value. Thus, there will likely be a numerical iGsiteRGey 7 The basis of this EAL invov the a ion in thes le o plant implied by the uncontrolled release. ExceedingýCJ EAL1 41A or 45 is an indicationR of an uRncnrolled release.Explanation/Discussion/Definitions:

The column "UE" liquid release values in Table R-1 represent two (2) times the High Alarm setpoints ( except 2R1 8 which is 1.5 times) associated with the specified monitors.

The High Alarm setpoints are obtained from channel calibrations procedures as listed in the reference section of this bases.Salem Page 4 of 6 Rev. 0 (draft E)EAL#: RU1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Instrumentation that may be used to assess this EAL is listed below:* Containment Fan Coil Process 1(2)R13A/B (Upper Range is 1.00E+06 cpm)Service water is used as the cooling medium for the containment fan coil units (CFCUs)and could be contaminated if the cooling coil leaks with containment pressure above Service Water pressure.

Since the Service Water System discharges into Circ Water and then back to the river, the fan cooler units will be indirectly monitored for radioactivity.

This is done through the use of two monitors for the five fan coolers. The two monitors sample two of the three Circ Water headers that contain Service Water used to cool the CFCUs just before it discharges back to the river. Alarms on these monitors would be indicative of a CFCU leak but could also be associated with other systems including from the pathways monitored by the R1 8s, R1 9s and the R37, which also discharge into Circ Water and are monitored by the 1(2)R13A/B.

If simultaneous Rad Alarms are received on an R1 3 monitor along with any RI 8s, R1 9s or R37 monitor, then the source of the Rad effluent may not be a CFCU leak and further investigation would be warranted.

However, exceeding the EAL threshold value for > 60 minutes should result in Unusual Event classification even if the exact source remains questionable.

Liquid Radwaste Disposal Process 1(2)R18 (Upper Range is 1.OOE+06 cpm)This channel continuously monitors all Waste Disposal System liquid releases from the plant. Automatic valve closure action is initiated by this monitor when a high radiation level is indicated and alarmed in the Control Room. Liquid Radwaste discharges to Circ Water which then discharges to the Delaware River.This Unit 1 EAL threshold is based on 2 times the High Alarm Set Point as defined in the Channel Calibration procedure.

This Unit 2 EAL threshold is based on a value that is approximately 1.5 times the High Alarm Set Point as defined in the Channel Calibration procedure which ensures that the threshold value is within the upper range of the monitor.Since the ranges of the 1(2) R18s monitors do not support EAL threshold values of 200 times the high alarm value, no Alert threshold is provided on Table R-1. If the release pathway could not be isolated as expected, the EC should refer to EAL RA1.3 for Alert threshold values based on sample analysis.* Steam Generator Blowdown Process 1(2)R19A-D (Upper Range is 1.00E+06 cpm)Each of these channels (four channels per unit) monitors the liquid phase of the steam generators for radioactivity, which would indicate a primary-to-secondary system leak.The four steam generator blowdown sample lines each have a radiation monitor. A high radiation alarm signal will close the No. 12 (22) steam generator blowdown tank inlet Salem Page 5 of 6 Rev. 0 (draft E)EAL#: RU 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 valves and the steam generator blowdown isolation valves on the affected steam generator.

Non-Rad Liquid Waste 2R37 (Upper Range is 1.OOE+06 cpm)The non-radwaste basin provides a potential release path due to the fact that steam generator blowdown is directed to the basin during plant startup. This monitor provides for continuous monitoring of the discharge from the non-radwaste basin. Non-Rad Liquid Waste discharges to Circ Water which then discharges to the Delaware River.Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AUl Example EAL #2 2. Salem ODCM Section 3.3.8 -Radioactive Liquid Effluent Monitoring Instrumentation

3. Salem ODCM Figures 1-1 and 1-2, Liquid Release Flow paths for Unit 1 and Unit 2 4. UFSAR Section 11.4 Radiation Monitoring

5. PSBP 315733(4)

Radiation Monitoring System Control Manual 6. S1($2).IC-CC.RM-0097/98, Channel Cal for 1/2R13A/B 7. S1(S2).IC-CC.RM-0028, Channel Cal for 1/2R18 8. 51($2).IC-CC.RM-0029/30/31/32, Channel Cal for 1/2R19A/B/C/D

9. S2.IC-CC.RM-0060, Channel Cal for 2R37 Salem Page 6 of 6 Rev. 0 (draft E)EAL#: RU1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 2 times the ODCM for 60 minutes or longer EAL# & Classification Level: RU1.3 -UNUSUAL EVENT Mode Applicability:

All EAL: Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > Table R-2 column "UE" AND_> 60 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Table R-2 Effluent Sample Classification Thresholds Release Point Sample ALERT UE NG 6.40E-01 pCi/cc 6.40E-03 VCi/cc Plant Vent 01-131 5.60E-05 VCi/cc 5.60E-07 tCi/cc U/)Unmonitored Isotopic 200 x ODCM 3/4.11.2 2 x ODCM 3/4.11.2 Containment Fan Coil Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1-2 Liquid Radwaste Disposal Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1.2 Steam Generator Blowdown Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Chemical Waste Basin Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Unmonitored Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Salem Page 1 of 5 Rev. 0 (draft E)EAL#: RU1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Basis:[Ref- r Appendix A for a detaied basis of the mdiole gica effluent !C/EALs.]The E.mergency Coordinator should not wait until the applicable time has clapsed, but should declare the eVent as Soon as it is determincd that the conRdition Will likely exceed h appiable time.This IGEAL addresses a potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[These cotrols are located ip the Off- site Dose Calculation Manual (ODCM4), and for plants that have neGt implementedf Generic Letter- 9 4n- the R, ;-,l-,i,,o Effluent T, -,io Specificatuonsiu (RETS)t ]The occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.[

sites m find 4 .............

gaseous and l4guid r-eleases wMth separate EA Ls.]The RETS-multiple of two times the ODCM limits a-e-is specified in AU! and A EAL RU1.3 only to distinguish between non-emergency conditions, nd from each other. While these-this multiples obviously corresponds to an off-site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.[Releases shoquld net be pror-ated or aver-aged.

For- ex ample, a r-elea Se Gxcee d~nq 4x CDCM for 30 miutes does not meet the thresh'Oj This EAL includes any release for which a radioactivity discharge permit was not prepared, or a release that exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm setpoints, etc.) on the applicable permit for -> 60 minutes.EAL #!This EAL addresses radioactiVity releases, that for whatever reason, cause effluent radiation moenitor readings to exceed the threshold identified in the IC.This E=AL is intended for sites that have established effluent mon~itoring on non routine releas pathways for which a discharge permit would not normally be prepared.[The ODCM4 establishes a methodology for determininpg effluent radiation monpitor setpe4nt.The ODCM specifies t o'.. m and, fo gaseous rele ases, pres. cr'"bes the use of proe determined annual average meteorology in the most ,*limtg nPind Seeter- for she," ng GePmqpAtan t 'fth th e regulatory co~pmm1i PqtmenS. Th iS F £4L s hoE)uld be dete rmihe Pd- usingi this m4e th odology.]EAL #2 Salem Page 2 of 5 Rev. 0 (draft E)EAL#: RU1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203-TisE.A.1a ddrFesses red ioactimty relcases, that for whatever rcason, cause effluent radiati;+ r4; + n nnAir +kn +kirnic'kriA idrirnflfie

i +k riI' c+ k~chir4 k i A hr k r rinr+h ;+ ioeh,rrr permit. This value may be associated with a plan1.ed batch release, or a cn.tinUous release path.[in either hase, t.he va!lueis .o. tabiahe !by .ODCM to wa.Fnof a releas that t .h EAL wil never be le ss than the s etpoipt establisheci by a Gp e~ifiG dli-sharge p erinnit.1 EAL #3 This EAL addresses uncontrolled releases that are detected by sample analyses, particularly on unmonitored pathways, e.g., spills of radioactive liquids into storm drains, heat exchanger leakage in river water systems, etc..AL #44 aon- #5 The 0.40 mRhr value in EAL #4, aRd the Site spec.ific value fr E-AL +Fs based onr a release rate no9t eXceeding 500 mr;eM per-yea.[s provded in the ODOM / RETS, prorated ever 8766 hours0.101 days 2.435 hours 0.0145 weeks 0.00334 months , multiplie by two, and rOun (500. 8766 x-2 .144-.]EAL #, and #2 directly correlate with the IC since annual average meteorolo.gy is requird to be used in sho)wing compliance With the 00CM and is used in calculating the alarm SctpointS.

EALs A4 and #5 are a fun.tion of m-eteor..g. h. Will likely be ditfeeRent from the !imiting an.ual average value. Thus, there will likely be a num.erical iRnosiStenGcy.

The underlying basis of this EALinvolves the degradation in the level of safety of the implied.Eby then rinnntrnllid rFero EXnredAnn FAL #4 er #is a Rn inRdiGnt+n Af aRn 6nrnntrnU!4 re ýe-se.Explanation/D iscussion/Definitions:

Releases in excess of two times the site Offsite Dose Calculation Manual (ODCM) Section 3/4.11.1 or 3/4.11.2 limits that continue for 60 minutes or longer represent an uncontrolled situation and hence, a potential degradation in the level of safety. The final integrated dose (which is very low in the UNUSUAL EVENT emergency class) is not the primary concern here;it is the degradation in plant control implied by the fact that the release was not isolated within 60 minutes.Table R-2 provides calculated radiological release noble gas and iodine sample concentrations that equate to a release that is 2 times the ODCM limit (Section 3/4.11.2) of 500 mRem/year as well as specifying liquid release effluent sample streams 2 times the ODCM limits (Section 3/4.11.1).

Each Salem unit has a single gaseous release point (Plant Vent) for which a sample concentration threshold has been calculated.

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: RU 1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AU1 Example EAL #3 2. Off-Site Dose Calculation Manual, Section 3/4.11.1 -Liquid Effluents 3. Off-Site Dose Calculation Manual, Section 3/4.11.2 -Gaseous Effluents 4. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)Salem Page 4 of 5 Rev. 0 (draft E)EAL#: RU1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: RU 1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 200 times the ODCM for 15 minutes or longer All RAI.1 -ALERT EAL: VALID gaseous monitor reading > Table R-1 column "ALERT" AND> 15 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Salem Page 1 of 6 Rev. 0 (draft E)EAL#: RA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent 1 R41D + 2R41D 0Effluent Noble OR oa Efun NobleneR 8.48E+09 pCi/sec 8.48E+08 pCi/sec 4.84E+07 pCi/sec 4.84E+05 pCi/sec CU Ga SPDS combined O Unit 1 + Unit 2 release rate Containment Fan Coil 1(2)R1 3A/B ---- ---- 1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U1= 5.50E+05 cpm Radwaste N/A* Disposal See EAL RA1.3" Process 2R18 U2= 9.90E+05 cpm ,J Steam 1R19A-D U1= 6.40E+05 cpm UI= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 ---- ---- 3.60E+05 cpm 3.60E+03 cpm Waste* For high radiation conditions on Letdown Line Monitor 1 R31A (2R31), refer to EAL SU7.1 Basis: rDefer to A-pend4i A for a dtail. , d o f the ffluenIIt q I I.I I tj Utj Eb %I J- U iy~ U ! U!I !Idlj! b twI IUU F I UL VVdIt U1 itil IIU JIU UU III U Ug U ,UL c'kni wlr4 Isr n nh 5 ntnn+ ,ncT-rnrr nn, 4~ iý ,~m ,+ kn+ +kiý r's11~,-r M-1-AI Iýýes-,~n A 4k-This 1-GEAL addresses an actual or substantial potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[These ..,trols areý Ioated in the Off Site Does Clu Ation Manual (ODCf and frpntththve no9mlmne i,- Ltter 89 01, i the Radiological Lnt Te hnial Spec(ificatons (RETS)] The occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.r ~ effl~rI C.iF,'-4 ;,f 4ý -1,4--_'j I;_' ;_j __ I- -__ -ý -41, rlz7vj 11- 01-0 1 1 -V I I, J_ I, __ V-1 -_- --- --I-- ý .. -ý.separ-ate EAL&-J The threshold values that equates to a RETS-multiple of two hundred times the ODOM limits are-is specified in AUl RUl and AA! EAL RAI.1 only to distinguish between non-emergency conditions, and from each other. While these-this multiples obviously corresponds to an off-Salem Page 2 of 6 Rev. 0 (draft E)EAL#: RAI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.[To a Fro a,',tio near .liear escGaation path, a alue should be rough!btween the AU! value a. dthe value calculated fe,,A-S! The vlue wil be based en r-adiation monitor read-,'ngS t9 eeed 200 times the Te-hnical SpecifiGatin ,imit and releases are not teim,, ated within 15 mtinutes.

The QDC, estabishes a methodologyf det'enr,43gl effluent radiation monitor- setphints.

The ODCM sper; fi , rG;fl t Sovr an4d, for gsosreleases, pr-escribes the use of pre dletermined ann~ual aver-age mneteoroelog th mos06t limiting downwind soector for: showing cmlacwihthe regulator-y commitments.

This EAL ca bendetermined sig this me thodolog' if apprenopiate.]

[Releases should not be prorated or averaged.

For example, a r-elease ex~eecding 6 0 ODCM4 for- 5 minutes does not meet the thr~eshold.]

This EAL incluides any release for Which a radioactivity discharge permit was not.prepared, or a release that eXceeds the conditions (e.g., minium dilUtion flow, maximum diScharge flow", ala rm sctpo intS, etc.) on the applicable perlmit_.EAL #1-This EAL is intended for sites that have established effluent monitoring on non-routine release pathways for which a discharge permit would not normally be prepared.EAL #2 This EAL addresses radioactiVity releases, that for whatever reason, cause effluent radi;atin rmonitor readiRngS o exceed the threshld ideRntified iR the IC established by the discharge permit. This value may be associated with alanned batch rlease-, o.a continuous release path-.[IR the i tab'Ashd by the ODCM to warn of a release that is nottin compliance with the PETS. Indexi4g the AL to the QDCM, set4pgots in this manner- i .i;nsure that the ,aA will never be less than the setpoint established by a specific discharge permit.]EAL #3 This EAL addresses uncontrolled releases that ape detected by sample analyses, pa~iuTGlary on pathways, e.g., spills of radioactiveliquids into storm drains, heat, exchanger leakagein river water systems, etc-.E:A1- 414 and #5 The 10.0 mRnhr value in EAL #4 , and the site specifc ;value for EAL #5,is based en a release 'rate not exceeding 500 mnrem per-yea.Salem Page 3 of 6 Rev. 0 (draft E)EAL#: RA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Pse provided in the ODCM4, / E-TS, prorated over 87-66 hours, m~ultiplied by 200, an roeunded.

(500 --8766 ), 200 -1141].EAL #I and #2 directly correlate with the IC SiRce annual average is-required to- be used in showing comnpliance with the ODOMt. an-d is_ Used in calculatingthe alaFrm setpointS.

E=AI- 41A and #5 arc a function of actual mneteorology, which willlieyb different fromn the lim~iting annu~al average value. Thus, there will likely be a numerical The underlin basis of th is EAL invo~lves the degradation in the level of safety of the plant.implied by the uncontrolled release. FXeeeding EAL5 44- or #5 is an inR4ieaiý-f-a-n un-ncontfrollerd -relcIase.Explanation/Discussion/Definitions:

The column "ALERT" gaseous release value in Table R-1 (Unit 1 + Unit 2) represents two hundred times the associated effluent monitor alarm setpoint.

This setpoint is set to preclude exceeding the ODOM release rate limits associated with the specified monitor.The plant vent monitors (R41) sample and detect noble gases and collect samples of particulates and iodine discharge through the plant vent. Channel D (R41 D) provides the gaseous effluent release rate (pCi/see) by combining (product of) the on-range R41IA through R41 C with plant vent flow (ce/see).Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AA1 Example EAL #1 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. UFSAR Section 11.4 Radiological Monitoring

4. PSBP 315733(4)

Radiation Monitoring System Control Manual Salem Page 4 of 6 Rev. 0 (draft E)EAL#: RAI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Salem Page 5 of 6 Rev. 0 (draft E)EAL#: RAI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 6 of 6 Rev. 0 (draft E)EAL#: RAI .1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 200 times the ODCM for 15 minutes or longer EAL# & Classification Level: RA1.2 -ALERT Mode Applicability:

All EAL: ANY VALID liquid monitor reading > Table R-1 column "ALERT" AND> 15 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: RA1.2 SGS ECG -EAL Technical Bases EP-SC-111-203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent 1R41D + 2R41D 0Effluent Noble OR Ga EPetoloR 8.48E+09 pCi/sec 8.48E+08 pCi/sec 4.84E+07 pCi/sec 4,84E+05 pCi/sec tu) a SPIDS combined CD Unit 1 + Unit 2 release rate Containment Fan Coil 1(2)R13A/B

--- 1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U 1 = 5.50E+05 cpm Radwaste N/A-Disposal See EAL RAI.3" Process 2R18 U2= 9.90E+05 cpm-J Steam 1R19A-D U1= 6.40E+05 cpm UI= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 ---.---- 3.60E+05 cpm 3.60E+03 cpm Waste* For high radiation conditions on Letdown Line Monitor 1R31A (2R31), refer to EAL SU7.1 Basis: rRefor to Anendix A for a detalled banis of th1 r-di- !-oI --/ effF'-nt IC!EAL.4 1*~~**~ -.-.-..I 71- E= f, A; + t' ie4l + ;+ +N +k i; k! +; 11 i eh'" j ,o. ........,-. o ti ,4ta +'. .,;;,...m,-hul de -lare the event as Soon as it is determined that the conditionR willlkely exceed th appie44-,~etme.

This IGEAL addresses an actual or substantial potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[Therse .,,tra/a ... ,,cated inp.the Qffa-ite Dose G 1-1c Mau, (CD CM), and fbF pilanta that haý vnot- mrp~elmene ,Gene.,.;-

La 99 01, in the Radio/a gical Effluent Terhnical Specification (RE3Q .h occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.ro A'- 4 ; 14 4,4 -----'i Il- ;_j -- I- --- -1. 11,41,~spraeEAL&1 The threshold values that equate to a RET-S-multiple of two hundred times the ODOM limits a-e4sare specified in AUI RU! andAA! EAL RA 1.2 only to distinguish between non-emergency conditions,and from e-ach other. While these-this multiples obviously corresponds Salem Page 2 of 5 Rev. 0 (draft E)EAL#: RA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 to an off-site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.[To a reafliS.i near. iear esc.alation path,, , valUe ShGUid be dUgh, haf-wa y-.etweeng the AU! value and the vae GUacated for AS l, The value wl be based on r-adiation monitor to exceed 200 times the Technical spanifinatin fimit and releases a.r.e nt terminated within 15 minutes, The establishes a ,methodology for-determining effluent readiatio monitor sewtpohts.

The ODOM dpietifiets de fault s recare term an, for e aseous releases, prte o rites the use of prou determined annual aveage meteorgology in th mosetp lming deo nn sector for- showg opeance th the regulatoryc This EAL apn be dfoterminede using this methodology if appreopriateo

[Releases should not be perorated 9o avraged. For exeample, a release exceeding 60X ODi4for5minutes doSes not meet the threshn ol.]This EAL includes any release for which a radioactivity discharge permit was not prepared, or a release that exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm setpoints, etc.) on the applicable permit.EAL41 This EAL is intended for sites that have established effluent monitoring on non-routine release pathways for which a discharge permit would not normally be prepared (Containment Fan Coil, SG Blowdown & Chemical Waste Basin) as well as planned batch releases for which a radioactivity discharge permit is prepared (Liquid Radwaste Disposal).

EAL #2 This EAL addresses radieaGtivity releases, that for whatever reasnr, cause effluet radiation mronitor readingso the threshold identified in the IC established by the r.adioactivity discharge permit. This- value may be assEocO-iated with a planned batch release, GF a continuo19us release path-.[in eiter case, the vahle is establish-d by the ODCn 4 to warn of a r.eleae that is npo pn complince with the RETS. !ndexing the EAL to the CDCM setpoints in this manner ins&uros that the &AL wil nevern beless than the &etpoint establish e b) a specii discharge permit.]EAL #3 This EAL addresses uncontrolled releases that are det-cted by sample aRalyses, particularFly OR unmRonitored pathways, e.g., spills of radioactive liquids into stormn drains, heat exchanger leakage in river water systems, etc-.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: RA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EALs #4 and #5 The 10.0 mRihr value in EAL #4 , the site specific value f.. r EAL #5,is based on a release rate n eding 500 mremperea.

[As provided in the DQAC!/RETS, p t7,,.,66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months , by 20-, an runded. (500:- 8766 -200 -- 44.,4.EAL #1 and #2 directly correlate with the IC since annual average meteorology i-s requiFed to be used in shoWing complianc

.with the 0CM and is used in the alarm EALs #4 and #5 are a function of actuall meteorolFogy, which likely be dLiffrent from the Iiting annual aeagev Thus, there will likely be The underlying basis of this EAL inVolves the degradation in the levelof safety of the plant implie by, theuncontroll~ed release. EcdigEAL #4 or #5 is an indication o~f anR ud releuae.Explanation/Discussion/Definitions:

With the exception of the R18 monitors, the "ALERT" column liquid release values in Table R-1 represent two hundred (200) times the High Alarm setpoints associated with the specified monitors.

The High Alarm setpoints are obtained from channel calibrations procedures as listed in the reference section of this bases.Instrumentation that may be used to assess this EAL is listed below: " Containment Fan Coil Process I(2)R1 3A/B (Upper Range is 1.00E+06 cpm)Service water is used as the cooling medium for the containment fan coil units (CFCUs)and could be contaminated if the cooling coil leaks with containment pressure above Service Water pressure.

Since the Service Water System discharges into Circ Water and then back to the river, the fan cooler units will be indirectly monitored for radioactivity.

This is done through the use of two monitors for the five fan coolers. The two monitors sample two of the three Circ Water headers that contain Service Water used to cool the CFCUs just before it discharges back to the river. Alarms on these monitors would be indicative of a CFCU leak but could also be associated with other systems including from the pathways monitored by the R1 8s, R1 9s and the R37, which also discharge into Circ Water and are monitored by the 1(2)R13A/B.

If simultaneous Rad Alarms are received on an R1 3 monitor along with any R1 8s, R1 9s or R37 monitor, then the source of the Rad effluent may not be a CFCU leak and further investigation would be warranted.

However, exceeding the EAL threshold value for > 15 minutes should result in an Alert classification even if the exact source remains questionable.

Liquid Radwaste Disposal Process 1(2)R1 8 (Upper Range is 1.OOE+06 cpm)Since the ranges of the 1(2) R18s monitors do not support EAL threshold values of 200 times the high alarm value, no Alert threshold is provided on Table R-1. If the release Salem Page 4 of 5 Rev. 0 (draft E)EAL#: RA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 pathway could not be isolated as expected, the EC should refer to EAL RA1.3 for Alert threshold values based on sample analysis.This channel continuously monitors all Waste Disposal System liquid releases from the plant. Automatic valve closure action is initiated by this monitor when a high radiation level is indicated and alarmed in the Control Room. Liquid Radwaste discharges to Circ Water which then discharges to the Delaware River.* Steam Generator Blowdown Process 1(2)R1 9A-D (Upper Range is 1.OOE+06 cpm)Each of these channels (four channels per unit) monitors the liquid phase of the steam generators for radioactivity, which would indicate a primary-to-secondary system leak.The four steam generator blowdown sample lines each have a radiation monitor. A high radiation alarm signal will close the No. 12 (22) steam generator blowdown tank inlet valves and the steam generator blowdown isolation valves on the affected steam generator.

Non-Rad Liquid Waste 2R37 (Upper Range is 1.OOE+06 cpm)The non-radwaste basin provides a potential release path due to the fact that steam generator blowdown is directed to the basin during plant startup. This monitor provides for continuous monitoring of the discharge from the non-radwaste basin. Non-Rad Liquid Waste discharges to Circ Water which then discharges to the Delaware River.Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AA1 Example EAL #2 2. Salem ODCM Section 3.3.8 -Radioactive Liquid Effluent Monitoring Instrumentation

3. Salem ODCM Figures 1-1 and 1-2, Liquid Release Flow paths for Unit 1 and Unit 2 4. UFSAR Section 11.4 Radiation Monitoring

5. PSBP 315733(4)

Radiation Monitoring System Control Manual 6. S1(S2).IC-CC.RM-0097/98, Channel Cal for 1/2R13A/B 7. S1(S2).IC-CC.RM-0028, Channel Cal for 1/2R18 8. Si(S2).IC-CC.RM-0029/30/31/32, Channel Cal for 1/2R19A/B/C/D

9. S2.IC-CC.RM-0060, Channel Cal for 2R37 Salem Page 5 of 5 Rev. 0 (draft E)EAL#: RAI.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

EAL# & Classification Level: Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Any release of gaseous or liquid radioactivity to the environment greater than 200 times the ODCM for 15 minutes or longer RA1.3 -ALERT All EAL: Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > Table R-2 column "ALERT" AND> 15 minutes have elapsed (Note 2)Note 2: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.Table R-2 Effluent Sample Classification Thresholds Release Point Sample ALERT UE NG 6.40E-01 pCi/cc 6.40E-03 iACi/cc.Plant Vent 0 1-131 5.60E-05 VCi/cc 5.60E-07 ViCi/cc Unmonitored Isotopic 200 x ODCM 3/4.11.2 2 x ODCM 3/4.11.2 Containment Fan Coil Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 ,_ Liquid Radwaste Disposal Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1.2 Steam Generator Blowdown Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Chemical Waste Basin Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Unmonitored Isotopic 200 x ODCM 3/4.11.1 2 x ODCM 3/4.11.1 Salem Page 1 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Salem Page 2 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Basis:[Refer to AppeAdix A for a b of the r-adiological effluent ,...-ALs]The Emergency C.ordinator should not wait until the applicable time hRas elapsed, bt should declare the event as sooEn as it is determined that the Gcondition Will likely exceed th appiable tPn,-This 4ýGEAL addresses an actual or substantial potential decrease in the level of safety of the plant as indicated by a radiological release that exceeds regulatory commitments for an extended period of time.Nuclear power plants incorporate features intended to control the release of radioactive effluents to the environment.

Further, there are administrative controls established to prevent unintentional releases, or control and monitor intentional releases.

[TheSe controlS a.e located intheOf site ,ose Caoc.,,ton Manuel (ODCM), and for- plants that have not mp1lemented Geper4c Leter- 99 1in4 ' te Radi,910gicaiEl e~ Technical Sp~fGaiP ( 5T).] The occurrence of extended, uncontrolled radioactive releases to the environment is indicative of a degradation in these features and/or controls.[Some sites may find it advantageous to address gaseous and liquid relcases with separa te The RET-S-multiple of two hundred times the ODCM limits aFe-is specified in AU! and RU1.3 only to distinguish between non-emergency conditions, and from each Ether. While these-this multiples obviously corresponds to an off-site dose or dose rate, the emphasis in classifying these-this events is the degradation in the level of safety of the plant, not the magnitude of the associated dose or dose rate.[To ensure a r-eaiStic near linear "e"~alatien path, a value should be selecteed r-oughly half way botw'Poen the AU! aýnd the "ý/ue Ga/'-!tedfor AS1 vl. The va~lue w/! be based on radiation monitor- r.a to eXeed 200 times the Technical .pecifiation lim.it an.d re.eases are Pot trminatd within ,mnutes. The ODGM establishe.

a methodology for fetem*m, g ... uent radiation rm;n.ite setpoipts.

The ODGAM specifies default source term& andý, for- gaseous releaseS, pro scrbeS the se46 Of p. de4,4,ed annual av, ,.. ,,t ,. ..... in the most /im/tn g. ,,.,pd s"toý. f, ,, e Q n,, compliance wit the regulatory om.mitment"s.

This E4AGan be deteFa4ined s

it appr-Gpriate.4

[Releases should not be prerated or- averaged.

Fer cx apie, a release ex..ee d,,g ODCM for 5 minute's does Pot m~eet the th~r-GSO4d.

This EAL includes any release for Which a radioactivity discharge permnit was net prepared, or-a EAL H!Salem Page 3 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Thos EAL is inteRded for sites that have established effluent mRnitoring on non routine relea pathways for which a diScharge permit would not normally be prepared.EAL-#2 This EAL addresses radiuoatrVlty releases, that for whatever reason, cause effluent radiatinr mnunonittoedpa to exceed the threshold idertified i the I etaidshed by t dradioetivit dichange reaadeing rivr wtehsytesgtc permit. This value may be associated with a planned batch release, or a continuous release path.[in either- case, the value ;s establi-shd db), the QDCM te warn of a relea se that ' sE not ni Om~pliance with the RETS. Indexing the EA4L to the ODOM sctpeints in this manner i .nsures that the9 E,4L will never- bc less than4 the setpoint established by a specific disc br~gep emit.]E=AL #3 This EAL addresses uncontrolled releases that are detected by sample analyses, particularly on unmonitored pathways, e.g., spills of radioactive liquids into storm drains, heat exchanger leakage in river water systems, etc.EALs #4 and #5 The 1 0.0 m~lhr value in EAL #4 , and the Site specific value for EAL #5, is based on a releases rate not exceeding 500 m~rcm per Fyear.[As provi/ed in the ODOM- RETIS, proratedf over-8766

hours, by 200, and rounded.(500 : 8766 x 200 -1 4.E=AL #1 and #2 directly correlate with the IC since annual average meteorology is required to be used i, compliance with the DGM and is used in calculating the alarm setpoints.

EALs .-.#and #5 are a func~tion of actuial meteoroloOgy, which Will likely be different from thc limiting annu1al average value. Thus, there will likely be a numerical Explanation/Discussion/Definitions:

Confirmed sample analyses in excess of two hundred times the site Offsite Dose Calculation Manual Section 3/4.11.1 or 3/4.11.2 limits that continue for 15 minutes or longer represent an uncontrolled situation and hence, a potential degradation in the level of safety. This event escalates from the UNUSUAL EVENT by raising the magnitude of the release by a factor of 100 over the UNUSUAL EVENT level (i.e., 200 times ODCM).Table R-2 provides calculated radiological release noble gas and iodine sample concentrations that equate to a release that is 200 times the ODCM limit (Section 3/4.11.2) of 500 mRem/year as well as specifying liquid release effluent sample streams 200 times the ODCM limits (Section 3.11.1).Each Salem unit has a single gaseous release point (Plant Vent) for which a sample concentration threshold has been calculated.

The required release duration was reduced to 15 minutes in recognition of the raised severity.Salem Page 4 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Basis Reference(s):

1, NEI 99-01 Rev. 5, AA1 Example EAL #3 2. Off-Site Dose Calculation Manual, Section 3/4.11.1 -Liquid Effluents 3, Off-Site Dose Calculation Manual, Section 3/4.11.2 -Gaseous Effluents 4, Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)Salem Page 5 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 6 of 6 Rev. 0 (draft E)EAL#: RA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 100 mRem TEDE or 500 mRem Thyroid CDE for the actual or projected duration of the release All EAL# & Classification Level: RSI.1 -SITE AREA EMERGENCY EAL: VALID gaseous monitor reading > Table R-1 column "SAE" AND Dose assessment results are NOT available AND_ 15 minutes have elapsed (Note 1)Note 1: If dose assessment results are available, declaration should be based on dose assessment (EAL RS1.2) instead of gaseous monitor values. Do NOT delay declaration awaiting dose assessment results.The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: RS 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent 1R41D +2R41D o Effluent Noble OR o 8.48E+09 pCi/sec 8.48E+08 pCi/sec 4.84E+07 pCi/sec 4.84E+05 pCi/sec SGasSPDS combined CD Unit 1 + Unit 2 release rate Containment Fan Coil 1(2)R13A/B 1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U1= 5.50E+05 cpm Radwaste N/A Disposal See EAL RAI.3" Process 2R18 U2= 9.90E+05 cpm-" Steam 1R19A-D U1= 6.40E+05 cpm U1= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 3.60E+05 cpm 3.60E+03 cpm Waste t I I I I* For high radiation conditions on Letdown Line Monitor 1 R31A (2R31), refer to EAL SU7.1 Basis:[Refer- to Appendi A for a detaIed basis of the effluent , AEIaLs.I]This IG-EAL addresses radioactivity releases that result in doses at or beyond the site boundary that exceed 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.[While these failures are addressed by other ,GsEALs, this 4G-EAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.1-rA IF 4-11 4r-,;, U' LA I ;L ; L '.'-;' " ;-A/AI ,Il.lL ; 'S:t,';tF

C ," ;;; L;;;; TTL;; .; L U.';;;.j L;; ALA L L;;A L;rVr_," TL;1LA I , L " LU;'I' L,';;4v.4Thnt (t.'CrFl)

F1 r fhp of rnncp nf th.. !fl/!FAI C q thp dog rif ntitv, tpthil Pffcrf1/2 dp...equivalent (TEDE), as defined in 10 CFR 20, is u~sed in lieu of "...sum of E=DE= and CE=DE...." T7,rw IZPA -An (2 -if,4npr-,nt rpin4ino Fr-Na #l 4 in a ac- .n,4id 1-b *J-aniLw-Iricn-'o,.

fclrfnrrcs 1.4nIA ,-rnoff e4 ;-4 r f-N t- Ir,- Ini~ r'h~i;1 IJA ;r4~r rng HI Ifilihi Ii IP ri fn~- #,,b ,-/ ' l C fr, ra-~TVJrI LAL LLL IAVLALLLALLLALLLALLIL UL LDIIL CIJ ALA %fI'. A IIJ ULAIIALL LAIL LL IALI.A IA/;fh6 fA^1CILn -~F #I' ;_#~C 1rA- Ira/I Ir, ~ hf.,'J#,c.rmarrr~irI~~~rr rr-fThe TEDE dose which forms the bases for the specified effluent monitor threshold is set at 10% of the EPA PAG, w'"hile the 500 mrem thyroid CDE was. established in consideration of+k-a I --r.-r -+,- -- 4k- D DA(2 ,--. TRZIN --,-- -M,,.-;- -'INEC I Salem Page 2 of 5 Rev. 0 (draft E)EAL#: RSI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL#!The Site-&peificTable R-1 monitor list in EAL #1 should includes effluent monitors on all potential release pathways.[Thý emnito reading EALs should be determ~ined using a d-se assessment method that b c a ,f the dosevalues specified in the 1G. since doqses ar. e gne.%FalyGt mognitor~ed in real! time, it is suggested that a.release duration of one hour bo assume-dand that th EA° be based On a site .pecifi, boundary. (or beyond) dose of 100 mr.em whole bed or 500 mFn mthyr.id in hour, WhicGheVo ,o /imiting (as was done for 4ALs #2 and#4). if in dividue site aia~ySes indicate a meten r w, her dureatio for the prito r ingh tE substantial presut of the asestim et i eayse d, the lnger duatten should be useada]or ~ "E ea inict thats usihrcasfcainiarned.

fFo dthisreason, Amergendcy

[The ment lgy uoed should be the sae sthoe sedfor o antusn monitoal meadilg .The same sourae torm (noble gases, part. s anheamgent) may also -be asedas logj as it1 m-1aintains a r-ealistic andn oear linear- esca -Atn between the EALe fbFthe fo ,r,'c GlSiiaes lfr-pr ea, at'o do not r-si 4:9 oh s f so _UG traifal thea lthe lassifivales are ursealisticalgy high, Or- if clorrelatn between the values an dose assessment values does not exist o thren cnsider using aL .Gcident8s ,r- term for ASi and4 AGI calcý-Iulations.]

Since dose assessment is based on actual meteorology, whereas the monitor reading EAL is not, the results from these assessments may indicate that the classification is not warranted, or may indicate that a higher classification is warranted.

For this reason, emergency implementing procedures should call for the timely performance of dose assessments using actual meteorology and release information.

If the results of these dose assessments are available when the classification is made (e.g., initiated at a lower classification level), the dose assessment results override the monitor reading EAL.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: RS 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Explanation/Discussion/Definitions:

This EAL address gaseous radioactivity releases, that for whatever reason, cause effluent radiation monitor readings corresponding to site boundary doses that exceed 100 mRem TEDE.The column "SAE" gaseous effluent release values in Table R-1 (Unit 1 + Unit 2) correspond to calculated doses of 10% of the EPA Protective Action Guidelines (TEDE).The plant vent monitors (R41) sample and detect noble gases and collect samples of particulates and iodine discharge through the plant vent. Channel D (R41 D) provides the gaseous effluent release rate (pCi/sec) by combining (product of) the on-range R41A through R41 C with plant vent flow (cc/sec).If dose assessment results are available, EAL RS1.2 would dictate the need for a Site Area Emergency classification due to abnormal radiation effluents.

Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AS1 Example EAL #1 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. UFSAR Section 11.4 Radiological Monitoring

4. PSBP 315733(4)

Radiation Monitoring System Control Manual Salem Page 4 of 5 Rev. 0 (draft E)EAL#: RSI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: RS 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 100 mRem TEDE or 500 mRem Thyroid CDE for the actual or projected duration of the release EAL# & Classification Level: RS1.2 -SITE AREA EMERGENCY Mode Applicability:

All EAL: Dose assessment using actual meteorology indicates TEDE 4-day dose > 4.OE+02 mRem or Thyroid CDE dose > 2.OE+03 mRem at or beyond the MINIMUM EXCLUSION AREA (MEA)Basis:[Refer to AppendixA for ade tailed basis of the radiological effluep 1t!CEALs.]

This IG-EAL addresses radioactivity releases that result in doses at or beyond the MINIMUM EXCLUSION AREA (MEA)site 199Udaiy that exceed 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.[While these failures are addressed by other ICs EALs, this 4--EAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.]

[The E=PA RA4G, are ex.pres.ed i, of the sum of the effectiv el.se equ,. .,ep, (EDE)9 aped the committed effective dlose cquivalent (CEDE=), or as the thyroGid committed d~os-e For- the pur.pose of thse !C/EALs, the dose quantity total effective dose equivalent (TEDE), a& defined i4 10 CFR 20, is used i lieu f , ,....sum f EDE= CEDE.'.. ," ThM FDA DA.4 m_.y::d~nrr nwrn.,rk..'

qry fhi'rnP. nnn crrri n /.tnrP A,iJ /.qr The EPA P-4G OUidaPGO n=Vid,99 fGF t" U-50 RdUlt thUP04 dG&e GGPýýF& .GP faGAqr-& "Pluellpr 11 4 ;,4 n = "441,' It-=A 1 IF- k ftIj" '.,tA tLS."Fl I t ItA e e- t- t" t7C E Lt ttV n. t- LIt stfl L '.'.L. I. t rn) '..fl I" vL I S' At ' Vt. NS.' .IJ~With thcxc.rP O-f thP- .C~fttP~q01.n11r4Pdr in thP f iitv rnnrnnnnv nnnjncy 7Ofl 1 Vj-{The TEDE dose is set at 10% of the EPA PAG, while the 500 mrem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.J Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RS 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203-EAL #!1 The site liSt Ri EAL #1 Shou,,d incude ,, fluont monitoGrS o all poteRtial release pathways.[The monitor r.eading EALs should be detein,-ed using a dose ass...ment mthod thtck....from the do-- va-ue- din the .deaes are g It, At., it is suggested that a rel.a.e duration of o'ne hour- be assumed-, and that the EALs be- based o,4 a Site (or beyond) dose of 100 mr.em w--e bod Or 500 m-rem4 thyroid in One hour, W'hNheVOF ia3 mo-6mi a done for- EALa #f2 an ff4). if indivdual site analyeait i t ogro h~rdrto o thel period inwhcth subsatan tial portion of the activiy As released-, the long or dur-ation aho'dbuad]

T-he meteoroo used. a ould be the same as those ued for deterFiPning AUI! ad AAýmonitorr e ading EA41s. ThI me'a seur-G ter (noble gases, partGicuates, and halogensI) may also be used as long as it mantiaaraist-e-nd near linareaalatien bet teep the EA Las for- the four- GlcaSificationa.

if proper eSealatUons do not result from the use of the sacme sour-Ge term, if the cacltdvalues are unr-ealatically high, OF rif Gorm lotion betWeen the Vale n do ---9&Paent ý4le ~SPtX9, the GGi~FS' an aG aoetSG e~ term fo~rAS1 Since dose assessment is based on actual meteorology, whereas the monitor reading EAL is not, the results from these assessments may indicate that the classification is not warranted, or may indicate that a higher classification is warranted.

For this reason, emergency implementing procedures she~uld call for the timely performance of dose assessments using actual meteorology and release information.

If the results of these dose assessments are available when the classification is made (e.g., initiated at a lower classification level), the dose assessment results override the monitor reading EAL.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RSI .2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Explanation/Discussion/Definitions:

The dose assessment output on the Station Status Checklist (SSCL) is reported at varying distances from the plant as a TEDE 4-Day dose. This TEDE 4-day dose assumes a 4 hr release duration.

To obtain the approximate dose for a projected release condition of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the TEDE 4-day dose value would need to be divided by 4.A TEDE 4-Day Dose > 4.0E+02 mRem correspond directly to a TEDE dose rate value of 100 mRem/hr and exceeds 10% of the EPA Protective Actions Guides (PAGs). The Thyroid-CDE Dose > 2.0E+03 mRem correspond directly to an CDE dose rate value of 500 mRem/hr and exceeds 10% of the EPA Protective Actions Guides (PAGs) which was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.For the purposes of this EAL, the Site Boundary for SGS is the MINIMUM EXCLUSION AREA.Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

MINIMUM EXCLUSION AREA (MEA): The closest location just beyond the OWNER CONTROLLED AREA where a member of the general public could gain access. For Salem the MEA is 0.79 miles.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AS1 Example EAL #2 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. UFSAR 2.1.2.2, Boundaries for Establishing Effluent Release Limits Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RS 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 100 mRem TEDE or 500 mRem Thyroid CDE for the actual or projected duration of the release EAL# & Classification Level: RS1.3 -SITE AREA EMERGENCY Mode Applicability:

All EAL: Field survey results indicate closed window dose rates > 100 mRem/hr expected to continue for _> 1 hr at or beyond the PROTECTED AREA BOUNDARY OR Analyses of field survey samples indicate 1-131 concentration

> 3.85E-07 gCi/cc at or beyond the PROTECTED AREA BOUNDARY Basis:[Refer- tog Appendix A forF a de-tailed baSiS of the radiloica eflunt!c/A a.This IG-EAL addresses radioactivity releases that result in doses at or beyond the PROTECTED AREA BOUNDARY site boundapy-that exceed 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.[While these failures are addressed by other tOsEALs, this 4CEAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.1r--A F')A,ýX L_ X I- zc_ _Jý -0 T --f -- ý ----i FFF,- P T Q Qrfm A T P P r-1-04P 0QP--P0W14QAQnT ICr)CI equ,,,let (CDE-). For the purpose of these ICE'CALs., the dose quantity total effetve dse,;, -l ÷ I ' r ..n ..4,.A*- .4 ', -1 I f) 'l C7 1"D ;C a IC.I; ; , , 1 1- ." r some- 8st-ates-ha dcddt alculate child thyroid ODE=. UtL49ty l/E4A1s need to be consistn-.1;4h fhý cA rs c'ýFf.i-/pl rlns, ^s~ nU# ,;c fA ,- i -1p, -l ;--, s .,-,--- 1 ,__-.J -_.,1_,Z,_1,_., 1-1-1.11111.v Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RS1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203-[The TEDE dose is set at 10% of the EPA PAG, while the 500 mrem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.]The Site specific monitor list in EAL. #1 should include effluent monitor-s on all potenta release pathways-.

[The monitor- r-eading EALs should be determinecd using a dose assessment mnethe that back calculates from the do-se values specified in the 1G. Sinoe do~ses arc gen~erally not that the EALs be basedl on a sito specific bGu dr-I rý beyORdG wa done Ofo EA4 02 andl b or500 -mm thyroid in one hour, whlchever is me," ',imting (as was done ,,, ##4). if individf~

tQ11 Sit- Paicuses indicate a longer o* shoeir duragonloLdr h per'o i ~whic-tb substantial portion of the activity is releasedj the longer durationp should be used.]I!,[The meteeorolgy used should be the same as those udf9, determ7n4ng A91 and AA I enitoer r .eadng EALs. The same bsource term (noble gases, pafrculates, and halogens.) .ay ahso be used as iong as it ma4ta ins a reagstgc and near :knear- escaearon between the E/'L&9fo th-e four* classifications.

if pro-per e ScalatgenS do not r-esult fr-om the use of the same sourcGe term4, if the calculated values ar-e neafscl hgh, OF if GOFrnlatien betwenthe valuesan clos aasssmnt va~us doe o x-f the PP-'sdeF using1 an aG~idegt SGWume te~mfe A S I and AGI calculations I Explanation/Discussion/Definitions:

This EAL addresses a radioactivity release field survey 1-131 sample concentration or count rate that would result in a Thyroid CDE dose of greater than 500 mRem for one hour of inhalation at or beyond the PROTECTED AREA BOUNDARY.

This value exceeds 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.The Iodine-131 field survey sample concentration and count rate threshold is based on 1-131 dose conversion factors (DCFs) from EPA-400. The thresholds are based on a Thyroid-CDE Dose Rate of 500 mRem/hr for 1-131.For the purposes of this EAL, the PROTECTED AREA BOUNDARY is used as it is an easily determined location to obtain a field survey dose rate reading or to obtain a field sample.Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RS1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AS1 Example EAL #4 2. Off-Site Dose Calculation Manual, Figure 5.1-3, Area Plot Plan of Site 3. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RS1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: R -Abnormal Rad Levels / Rad Effluent I -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 1000 mRem TEDE or 5000 mRem Thyroid CDE for the actual or projected duration of the release All RGI.1 -GENERAL EMERGENCY EAL: VALID gaseous monitor reading > Table R-1 column "GE" AND Dose assessment results are NOT available AND> 15 minutes have elapsed (Note 1)Note 1: If dose assessment results are available, declaration should be based on dose assessment (EAL RG1.2) instead of gaseous monitor values. Do NOT delay declaration awaiting dose assessment results.The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: RG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -203 Table R-1 Effluent Monitor Classification Thresholds*

Release Point Monitor GE SAE ALERT UE Plant Vent IR41D + 2R41D o Effluent Noble ORE W a SPScmie 8.48E+09 pJCi/sec 8.48E+08 pCi/sec 4.84E+07 pCi/sec 4.84E+05 pCi/sec L5 Gas SPDS combined CD Unit 1 + Unit 2 release rate Containment Fan Coil 1 (2)R13A/B

---- 1.64E+05 cpm 1.64E+03 cpm Process Liquid 1R18 U1= 5.50E+05 cpm Radwaste N/A.Disposal 2R18 See EAL RAI.3 U2= 9.90E+05 cpm.Process" Steam 1R19A-D UI= 6.40E+05 cpm U1= 6.40E+03 cpm Generator Blowdown Process 2R19A-D U2= 8.30E+05 cpm U2= 8.30E+03 cpm Non-Rad Liquid 2R37 ---- ---- 3.60E+05 cpm 3.60E+03 cpm Waste* For high radiation conditions on Letdown Line Monitor 1R31A (2R31), refer to EAL SU7.1 Basis:[Rhfor to Appendix A for a detailed basic of the

.effluent IC/EA Ls.o.This -IGEAL addresses radioactivity releases that result in doses at or beyond the site boundary that exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and likely involve fuel damage.[While these failures are addressed by other IG-sEALs, this tc-EAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.]

r -ri- C77) A n A fý 1' 411.1"_ 4,;. -_J___ --, ,,, -4ýEDE Fn te GcommittG/ed fctive dse equivalet (CE=DE), or cctethyroid committed doo eqI44velet (E.Frtepr-poso of these !CIEALs, the dc atytt!efciedc equivalen

_TD1~ ~0 CER 20, is used .pf-e "...sum of EDE and CEDE=...-." Th e EP RA gudac prvie fo th es -ad -,ult thyroqid dose converSion factor-s.

Hwvr Jt' I11/4ISIL~tSIII.Iv SI. dp iripS fI LU'-p.ipgI~Jlinin..L.

.hliUS LI T~i rl Cf jjilu;fi 1C =AI pi lphpp pqqtp I I -I -ý --- -Y J1L____ _X41- ,ý-- ;_ It/--..... j, .....I V6-H ; i i i if ip if! f H_ f f Mp lbtcr ttle) " 1 0 -, .--I I I f Hf! h If If Hf if I -Or -ill i0f. eifffii i(IF 1,f "FiH, I[The TEDE dose which forms the bases for the specified effluent monitor threshold is set at the EPA PAG, the 5000 mre.. thyroid CDE wa.s established in; consideration of the 1;5 r;tip Af Rho FPA pA, for TFDF And thyroid CflF-Salem Page 2 of 5 Rev. 0 (draft E)EAL#: RG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL #1 The site-s9eGifiGTable R-1 monitor list in EAL #I should includes effluent monitors on all potential release pathways.[The mponitor-reading EALs should be de termi.n ed using a dose assesment method that back calculates from4 the dose values Spe cifiedl in the 1Q. Since doGSes are geneFraly not m~onitor-ed in real time, it is sugge stedl that a releasc duration of one hour be assme d-, an that the EALs be based on a Site Specific boundary (-or beyoend) d~ose of 1000 mr~em whol-e bodly or 5000 m~rem thyro-id in one hour- Kwihc bvr- is' more fimiting O' was done forF EALs f and #4). if led ir'iduel 64-P enaI'Y-es-indicate a longer- or sho~ter duration for- the period in whic the substantial portion of the ac-tivity is ireleascd, the' fleger- duration should be Used.][The m~eteor-ology used should be the same as those used for determining,49'1 endAA 1 monitor- reading EALs. The samge sourcGe term (noble gases, pariculates, and halogenis)

May alse be ued des long as it maintains a re alstiG and near linear escalation be~veen the EA41=ferthe follr Inassificetibp.

ifpr,9per-ecnalatons do not rn5Iul ktfro the use of the same sou4rce term4, if the caeculated values are unrealistically high, Or if co~rrelation between the vealuesan dose assessment values does not exist, Mhen consider usi'ng an accident source term for ASI and AGi cecuations]ep Since dose assessment is based on actual meteorology, whereas the monitor reading EAL is not, the results from these assessments may indicate that the classification is not warrantedT or May indicate that a higher, lassficatien is warranted.

For this reason, emergency implementing procedures should call for the timely performance of dose assessments using actual meteorology and release information.

If the results of these dose assessments are available when the classification is made (e.g., initiated at a lower classification level), the dose assessment results override the monitor reading EAL.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: RG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 Explanation/Discussion/Definitions:

This EAL address gaseous radioactivity releases, that for whatever reason, cause effluent radiation monitor readings corresponding to site boundary doses that exceed 1000 mRem TEDE.The column GE gaseous effluent release values in Table R-1 (Unit 1 + Unit 2) correspond to calculated doses of 100% of the EPA Protective Action Guidelines (TEDE).The plant vent monitors (R41) sample and detect noble gases and collect samples of particulates and iodine discharge through the plant vent. Channel D (R41 D) provides the gaseous effluent release rate (pCi/sec) by combining (product of) the on-range R41A through R41 C with plant vent flow (cc/sec).If dose assessment results are available, EAL RG1.2 would dictate the need for a General Emergency classification due to abnormal radiation effluents.

Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AG1 Example EAL #1 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. UFSAR Section 11.4 Radiological Monitoring

4. PSBP 315733(4)

Radiation Monitoring System Control Manual Salem Page 4 of 5 Rev. 0 (draft E)EAL#: RG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: RG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

EAL# & Classification Level: Mode Applicability:

EAL: R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 1000 mRem TEDE or 5000 mRem Thyroid CDE for the actual or projected duration of the release RG1.2 -GENERAL EMERGENCY All Dose assessment using actual meteorology indicates TEDE 4-day dose > 4.OE+03 mRem or Thyroid CDE dose > 2.OE+04 mRem at or beyond the MINIMUM EXCLUSION AREA (MEA)Basis: rm_;-Nr f,- A ~~4~ A F~r~ p 1 pfý L~r ' rF *I-irnvI^,C -k, I i -;F---,, IC' IIA I, I.This 4G-EAL addresses radioactivity releases that result in doses at or beyond the MINIMUM EXCLUSION AREA (MEA) site exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and likely involve fuel damage.[While these failures are addressed by other IGsEALs, this IG-EAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.1

£TeEPA-Asr Ix re~ssd in term of the suP4of the effc-tive deose'q'gvabllp

~ri d ,',I~ri ~ I~tr h~r n i,'.'r~~-f ffia i c lr, I'IAl q fi rin- " linnifi #f-f#n, Qf~t-fL1+;

r~.,-I.-.~ T~rW~a:-.4na fr'rt nila ;_ '._ _J ;_ I.,_ -4_.C r- rN r- -;I-~ ~ ~ 'J.. w, L .I k /, -~ __ II F-. if LAL t i i LA L I , '. L TI-ntA Ij= A QA y11tr, -nrfne i H He i it i ff f Hf-H E H 117iiFF ; i 4; r=; .0.nritilf fA tr^;,-4 e4 __ I- .iF-n fp Q I.k.,. I I IS. -j~L~~ V 1 ~FiL 'LLL i.J L iA iAA LI L t LiJ L? LAAALL U LALA! ----,IV Lraii.3i iiLLti L. I ?S rti' LA lA 4_4,ic kiiiI ,4 ;r4^,4r i- -1ýi I ýfii ,.I-dIr 14-~~r-1i,1 j r C'rI I U414- #, IC /AI1 14 IF-~ t' 1,-414 vtit.: LiI ."LA i Li iLA LA-LLALAA,, ;it LA VtL, ;ii? Li iL ifLa iitii =L Ul t tul 8ftvt tt'y-]ý !it f!Y 2tUt Mv. j I[The TEDE dose is set at the EPA PAG, while the 5000 mrem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.]Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RG1 .2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL#21 The site Specifhc Rmonitor list in EAL #" sheuld include effluent monitrs on oll potential releas~e-pathways.[T-he monitor- r-eading EALs should .be determinedf using a dose assessment metho that back .alou.,ateS from the dos.e Vallue. spe.ified in the !CG. Since does. are no.monitoed in real t.me, it..s suggestd dthata release duration of one hour- be ashsume, an that the EIALs be based on a site specific boundar, (or beyond)do se of 1000 mrem wmhie boiy or 5000 mrem hmyrnid in one hour-, wicthever is more limiting (as was done or EAL is and #4)~. if ind v-dL al site- _-analyeS indiate a longer or shoqrte, duration qfo the period in which the substantial porion of the astietys r y relessed-, the longer dufation should be used.][The used should be thesame as those used for determinng AUt and AAc monitor reading EALd. The same sourr ee erm (npoble gases-, doeate, asd halogens)

May also be used das long as it mgain~tains a r-ealistic and near linear- esalati..o betwveen the EA, forthefouro loagation.

if proepe iorm'ations do not result from thee use of the same so", taalb, f h theea' clasftd values are u (-eag.s , initiatedh, or if classifictween the values dose assessment values does net exist, mtni consider using an accident sr teFM for ASI and AGI Galculations.]

Since dose assessment is based on actual meteorology, whereas the monitor reading EAL is not, the results from these assessments may indicate that the classification is not warranted-, or may indicate that a higher classification is warranted.

For this reason, emergency implementing procedures shouI4-call for the timely performance of dose assessments using actual meteorology and release information.

If the results of these dose assessments are available when the classification is made (e.g., initiated at a lower classification level), the dose assessment results override the monitor reading EAL.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RG 1.2 SGS ECG -EAL Technical Bases EP-SC-111-203 Explanation/Discussion/Definitions:

The dose assessment output on the Station Status Checklist (SSCL) is reported at varying distances from the plant as a TEDE 4-Day dose. This TEDE 4-day dose assumes a 4 hr release duration.

To obtain the approximate dose for a projected release condition of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the TEDE 4-day dose value would need to be divided by 4.A TEDE 4-Day Dose > 4.0E+03 mRem correspond directly to a TEDE dose rate value of 1000 mRem/hr and exceeds the EPA Protective Actions Guides (PAGs). The Thyroid-CDE Dose >2.OE+04 mRem correspond directly to an CDE dose rate value of 5000 mRem/hr and exceeds the EPA Protective Actions Guides (PAGs) which was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.For the purposes of this EAL, the Site Boundary for SGS is the MINIMUM EXCLUSION AREA (MEA) distance.Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

MINIMUM EXCLUSION AREA (MEA): The closest location just beyond the OWNER CONTROLLED AREA where a member of the general public could gain access. For Salem the MEA is 0.79 miles.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AG1 Example EAL #2 2. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)3. UFSAR 2.1.2.2, Boundaries for Establishing Effluent Release Limits Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RG 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-203 EAL Category: EAL Subcategory:

Initiating Condition:

R -Abnormal Rad Levels / Rad Effluent 1 -Offsite Rad Conditions Off-site dose resulting from an actual or IMMINENT release of gaseous radioactivity greater than 1000 mRem TEDE or 5000 mRem Thyroid CDE for the actual or projected duration of the release EAL# & Classification Level: RG1.3 -GENERAL AREA EMERGENCY Mode Applicability:

All EAL: Field survey results indicate closed window dose rates > 1000 mRem/hr expected to continue for __ 1 hr at or beyond the PROTECTED AREA BOUNDARY OR Analyses of field survey samples indicate 1-131 concentration

> 3.85E-06 ItCi/cc at or beyond the PROTECTED AREA BOUNDARY Basis: refpr to An....ndi A for a aetai/ed-28i-S Of the effluent This addresses radioactivity releases that result in doses at or beyond the PROTECTED AREA BOUNDARYs-4ebwaý that exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and likely involve fuel damage.fWhile these failures are addressed by other ,-GsEALs, this I-,G-EAL provides appropriate diversity and addresses events which may not be able to be classified on the basis of plant status alone. It is important to note that for the more severe accidents the release may be unmonitored or there may be large uncertainties associated with the source term and/or meteorology.]

_[The E=PA PG are ex'pressed in terms of the sum of the effeciv dose equivale L.~~~ý y.'L. L TyiLiT i3iU iLW T JA T-i~XiA L i I L ICI -i,~Li iU ii -ij i C itiFIIi. U i c'fl "iiii Inri# r)I~Z Ir:^ fl,r --r,,,cr r fi f, 1',i C A I fc. rrini~i~i fr~fzI *ii f 1 ti i it mL ... i L i Lf fLl.'LiL Un'ILt .i..LL t iL l iL r 4 C ~ I: iI t VL iL l equ'*alent (TED, a/ d-efied in 10 CFR 20, is used in ieu of "...sum of EDE= and CEE...., The EPA4 RAG guidance proevides for- the usle adUlt thyroid dose conver-sion factor-s.

However, Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RGI .3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 some states hav d.eided to calculate cGh4d thy)oid. CDE. tilty'1& !!EALs need to be consistept with those of the states involved in the facnifities emergencyý planning zonc.]{The TEDE dose is set at the EPA PAG, while the 5000 mrem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.]EAL I The ---e-cc;fG monitor list in EAL #1 61hou1d include eflet oios nalpoeta[The &4s should be determed using a dose assessment Mthed that back calcul~at9s from the doSe valueS specified in the 1C. Since do9seS aregnralno monitored.

in real time, it is suggestedtaarel M-1"9ea9se dluration of one hou be assumed, and that 1- th=4 L be based onq a Site &pec~'fic boundar-y (or beyond) dose of 1 000 mr-em whol!body or 5000 mrem thyroid in one hour, whichever is more limiting (as was done for EALs #2 and 4If ndividual site a..a...ses ndate a longer or sho.er duration for the-perio.-

nd the ubstntia portion of the.t aic~ ý rot ased, the longer- 'ration should be used.][The meteorology Usd ,, ou... d be9 the same as those used for determining AU. and AA , monitor Fead~ng EA4I ýý sam soIyrcnteirp (noble gases, palt4GUlate s, andK- halogens4) m4ay als be useda log-a&#4t-maintains a realistic aRG dga Rea r-esiaA9A-ion

'~nth~e-EALS for- the four- classifications.

if proper- escalations dor o rsutro the- use of the same isourc term, if the Ga'IG~la ted values are unreali-stically' high, or- if Giqrrelation between the valus ad dose assessm~ent values does not exist, then consider uiga qtsource term f~rAS4 andAGI -a'o u,,tions.j Since dose asse~ssment is based en acta- eeoooy wherFeas thc wonte.F F8~n EAL is no~t, the results fromn these assessments may indicte thaPt the- classificaio+isno wr-rted, o may indicate tlhat a- higher ciassificatioR is warranted.

Fr this emergency ipeetnprcdrssolcalfor the timely p~rac fds assessments using actual an. rese inRforma-tin.

if ,ultsof these -d-se assessments are avail-bl ..hen the classification) is made (e.g., initiated at-a--oweF classification level), the dos, results override the mnitor readiRng Explanation/Discussion/Definitions:

This EAL addresses a radioactivity release field survey 1-131 sample concentration or count rate that would result in a Thyroid CDE dose of greater than 5000 mRem for one hour of inhalation at or beyond the PROTECTED AREA BOUNDARY.

This value exceeds the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.The Iodine-131 field survey sample concentration and count rate threshold is based on 1-131 dose conversion factors (DCFs) from EPA-400. The thresholds are based on a Thyroid-CDE Dose Rate of 5000 mRem/hr for 1-131.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RG1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-203 For the purposes of this EAL, the PROTECTED AREA BOUNDARY is used as it is an easily determined location to obtain a field survey dose rate reading or to obtain a field sample.Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AG1 Example EAL #4 2. Off-Site Dose Calculation Manual, Figure 5.1-3, Area Plot Plan of Site 3. Salem Radiological EAL Setpoint Calculation Document NEI 99-01 Rev. 5 EALs (Attachment 6)Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RG 1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-204 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 2 -Onsite Rad Conditions/Fuel Pool Events UNPLANNED rise in plant radiation levels All EAL# & Classification Level: RU2.1 -UNUSUAL EVENT EAL: UNPLANNED water level drop in the refueling cavity, refueling canal or spent fuel pool (SFP) as indicated by ANY of the following:

.Confirmed SFP low level alarm (OHA-C35 SFP LVL LO)* RVLIS -Refueling Mode* Visual observation (local or remote)AND VALID area radiation monitor reading rise on ANY of the following:

1(2)R5 Fuel Handling Bldg* 1(2)R9 Fuel Storage Area* 1(2)R32A Fuel Handling Crane Fuel Handling Bldg (local monitor)* 1(2)R2 Containment General Area 130ft elevation o Temporary ARM Basis: This I-G-EAL addresses increased radiation levels as a result of water level decreases above irradiated fuel or events that have resulted, or may result, in unplanned increases in radiation dose rates within plant buildings.

These radiation increases represent a loss of control over radioactive material and represent a potential degradation in the level of safety of the plant.EAL fI-- "'HVUMU H I --H- I- -- ttid-v !1 'Q C, rnlm ri n L11 I 'n) C' !AIM Q r LZO A3 n -'2 --rý!=L .---1 -rn-n tinflfA rrniter-, aic-n d fnersnp (n,--,,;4 r-efuegg ,n e~ ,- r~ -epn ifa-, i ta l vhn .-ho#a- t 4lmJV *Is .nJ~lg L4~.IS '~.tEtAE A*.' AV'S 'tJL ~V. S'SS ASSf S~~J t'"C12 Vý C rr r-Orr"tn' Ulf Vy"t-v-cr

". Uryu" týr týj" U V-0 -t -M " t1- e- t-1 t-9!2 Salem Page 1 of 4 Rev.0 (draft E)EAL#: RU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 threshold m-.,.ay e to be bascd on "o~iat.4'ons of wateh m akeup rter9F i watoF&tor~age t.ank level.[!n !ight Of Reactor Cavity Sea!/failr-e incidentS at two9 different P-WRS and lOSS of Wa ter in the Spent F44el Pi'F-ueI TrFansfer Canal at a BlWR eXpficit Gover-age of these type's of events aý

, is appropriate given their potEn,'al for in.reaS. d doses topant Staf f.The refueling pathway is the a-&ie--jpeeifi-combination of cavities,4tubes, canals and pools in which spent fuel may be located. While a radiation monitor could detect an increase in dose rate due to a drop in the water level, it might not be a reliable indication of whether or not the fuel is covered.{For example, an refueling b4gE-ARM reading may increase due to planned evolutions such as head lift, or even a fuel assembly being raised in the manipulator mast. Also, a monitor could in fact be properly responding to a known event involving transfer or relocation of a source, stored in or near the fuel pool or responding to a planned evolution such as removal of the reactor head. Generally, increased radiation monitor indications will need to combined with another indicator (or personnel report) of water loss.]P o f this E, AI rq,. I un-e, stantin ofhe t1 , l act ,'q;,1ih,","ia'l v' ;,i-,din th ' of the monitor. lfo,-rmation Notie No. 90 08, ' R 85 Hazar-ds from Decayed Fe,,-l1" o,,i be .,nore din establishing EALs]For refueling events where the water level drops below the RP-VReactor Vessel flange.classification would be via EAL GU2CU3.1.

This event escalates to an ALERT per AA2-EAL RA2.1 if irradiated fuel outside the reactor vessel is uncovered.

For events involving irradiated fuel in the reactor vessel, escalation would be via the Fission Product Barrier Table for events in operating modes 1-4.EAL f2 This E=AL addresses increases in plant radiation levels that repreSent a loss o~f control ot radioactive material rcSUlting in a potential degradation in the level of safety of the plant.This EAL excludes radiation level increases that result from planned actiVities suh as use of radiographic sources and movemnent of r-adioactive waste materials.

A specific list ot7f ARMs is not requird -as it w.ould reStFrit the applicability of the Thr-eshold.

The intent is to identify lss of control of radioactive material in an monitore area.Explanation/Discussion/Definitions:

The Spent Fuel Pool (SFP) low level alarm actuates at 128' 2" from 1(2)LC650.

During refueling operations the reactor vessel and refueling cavity are flooded. During fuel handling operations, the fuel transfer tube (canal) will connect the refueling cavity and the Spent Fuel Pool (SFP). An unexplained lowering of refueling cavity level or SFP level can be Salem Page 2 of 4 Rev.0 (draft E)EAL#: RU2.1 SGS ECG -EAL Technical Bases EP-SC-111-204 an indication that these volumes are draining.

A drop in refueling cavity and SFP level may result in a SFP low-level alarm. This alarm would be validated by visual observation of lowering level (local or remote) in the refueling cavity or SFP.When the spent fuel pool and refueling cavity are connected, there could exist the possibility of uncovering irradiated fuel. Therefore, this EAL is applicable for conditions in which irradiated fuel is being transferred to and from the Reactor Vessel and SFP as well as for SFP drain down events.For a loss of shielding, the source of the radiation is within the refueling cavity or SFP. Without the shielding provided by normal water inventory in the SFP, equipment pool, and/or refueling cavity, radiation levels from irradiated fuel and activation products will rise substantially.

Area radiation monitors that may respond to a loss of spent fuel shielding are those located on the 130' elevation (Containment or Fuel Handling Building):

1(2)R5 Fuel Handling Bldg* 1(2)R9 Fuel Storage Area* 1(2)R32A Fuel Handling Crane Fuel Handling Bldg (local monitor)" 1(2)R2 Containment General Area 130ft elevation" Temporary Area Radiation Monitors Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AU2 Example EAL #1 2. SI(S2).OP-AR.ZZ-0003(Q)

OHA-C35 SFP LVL LO 3. S1(S2).OP-AB.FUEL-0002(Q)

Loss of Refueling Cavity or Spent Fuel Pool Level 4. S1(S2).OP-AB.RAD-0001(Q)

Abnormal Radiation 5. S1(S2).OP-AB.FUEL-0001(Q)

Fuel Handling Incident Salem Page 3 of 4 Rev.0 (draft E)EAL#: RU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 This page intentionally blank Salem Page 4 of 4 Rev.0 (draft E)EAL#: RU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 2 -Onsite Rad Conditions/Fuel Pool Events UNPLANNED rise in plant radiation levels All EAL# & Classification Level: RU2.2 -UNUSUAL EVENT EAL: UNPLANNED VALID area radiation monitor readings or survey results rise by a factor of 1,000 over normal levels (Note 7)Note 7: Normal levels can be considered as the highest reading in the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months excluding the current peak value Basis: Thi£ I$.-EAL addresses incre-sed radiation le-wls as a Feslofwtrlvldn eThe irradiat that have resulted, or may result, UNPLANNED increases in radiation dose rates within plant buildings.

These radiation increases represent a loss of control over radioactive material and represent a potential degradation in the level of safety of the plant.EAL !I[Site .pe..f.c indications in.. Ude instrumentation SUch as water level and local area-, ... -"----l 1- -ff- "1 -'P3a Y-91111-w-e-rnote obevto.Dpnig -a vai'lable leevee! ins trumen tatieon, the delar gonP threshold may nec d topbe b-ased on indications of water makeup rate or do area ac in water stor-age tank lvel.[Irigh ofRaco-avt-Sa aiue nient6 at two Gdif-feret PWRS and loGs Of AwateF in t et FuePtFrage ofth"ese tpes of e vathr-eshold Hi isapora e gvn their potwential for incrae doI topatsaf doses to .... staff-.]The refueling pathway is a site specific combination Of cavities, tubes, canals and water level, it might not be a reli-able indic-ationR of whether or not the fuel is covered.[For exa.mle, a refueling bridge ARM reg4;-g may inease. due to planned evolutio such as head lift', or even "a fuel assembly 68ing raised inR the manipulator mast. Also, a monitor Gould in fact bc properly responRding to a known event involving transfer or relocation Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RU2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-204 of a source, stored in 9F near the fuel peel or responding to a planned eVoautiv n such as raeoval of the reaors head. Generally, increased radiation moniter indications will need to combined with another indicater (operponnbiiel feport) of water ioss]Applofiatio of this EAL requines understanding of the acmtual aadiolagi.al condit prant inn/sity O, te monitor. nfoation:

Notie No. i0n08, "KR85 Haz-arfr Decaited Fuel" should be cnsidered in establishing radiation mneitor EALS.]For refueling events where the water level drops beiotw the RPV flage classificatin

\,ould be via CU2. This evert esoalates to an iAlert per AA2 if irradiated fsel outside the reactor vessel iS uncrvered.

For evntes ivolving irradiated fuel in the reator vessel, EAL t2-This EAL addresses increases in plant radiation levels that represent a loss Of eonttol ot radieacti'~e material resulting in a potential degradation in the level of safety of the plant.This EAL excludes radiation level increases that result from planned activities such as use of radiographic sources and movement of radioactive waste materials.

A specific list of ARMs is not required as it would restrict the applicability of the threshold.

The intent is to identify loss of control of radioactive material in any monitored area.ExplanationlDiscussion/Definitions:

Definitions:

UNPLANNED

-A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.VALID -An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1.- NEI 99-01 Rev. 5, AU2 Example EAL #2 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RU2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-204 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RU2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-204 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: R -Abnormal Rad Levels / Rad Effluent 2 -Onsite Rad Conditions/Fuel Pool Events Damage to irradiated fuel or loss of water level that has resulted or will result in the uncovering of irradiated fuel outside the Reactor Vessel All RA2.1 -ALERT Damage to irradiated fuel or loss of water level (uncovering irradiated fuel outside the Reactor Vessel) that causes a VALID high alarm on ANY of the following radiation monitors: Fuel Handling Bldg* 1(2)R5 Fuel Handling Bldg" 1(2)R9 Fuel Storage Area" 1(2)R32A Fuel Handling Crane Fuel Handling Bldg (local monitor)* 1(2)R41A Plant Vent Containment

1(2)R2 Containment General Area 130ft elevation* 1(2)R11A Containment Air -Particulate

1(2)R12A Containment Vent- Noble Gas" 1(2)R12B Containment Vent -Iodine Basis: This -=-EAL addresses increases in radiation dose rates within plant buildings, and may be a precursor to a radioactivity release to the environment.

These events represent a loss of control over radioactive material and represent an actual or substantial potential degradation in the level of safety of the plant.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: RA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204{These events escalate from A4U2-EAL RU2.1 in that fuel activity has been released, or is anticipated due to fuel heatup. This IG-EAL applies to spent fuel requiring water coverage and is not intended to address spent fuel which is licensed for dry storage.]EAL #1[Site speoff/ md/ca tins R-aY inc-ludfe intrlumentaio n/-uch as water leTl apdllocal area-isEAradiation monitors, andersoel (e.g., riefieling crew) repls. if acveala bne, /redl cdamerag menayremateden o ration monitr. Depeading my avabiable lovel instrumeiactivi , the deae araom threshold may need to be bcoi eeterkeup Fate or[WnlighteiofReactor Caviy Sct a- faincide nts attwo diurento PaRs and looss o water in the Spent Fuel Pat ruel Transfer Canal at a wh4et, orp neot heo ueagl of these types of eierts viahresold a# is approepriate giv heaipnt fo increased des to plann t staff]EAL #2 This EAL addresses radiation monitor indications of fuel uncovery and/or fuel damage.Increased ventilation monitor readings may be indication of a radioactivity release from the fuel, confirming that damage has occurred.

Increased background at the ventilation monitor due to water level decrease may mask increased ventilation exhaust airborne activity and needs to be considered.

While a radiation monitor could detect an increase in dose rate due to a drop in the water level, it might not be a reliable indication of whether or not the fuel is covered.IFor example, a refueling bridge ARM reading may increase due to planned evolutions such as head lift, or even a fuel assembly being raised in the manipulator mast. Also, a monitor could in fact be properly responding to a known event involving transfer or relocation of a source, stored in or near the fuel pool or responding to a planned evolution such as removal of the reactor head. Generally, increased radiation monitor indications will need to combined with another indicator (or personnel report) of water loss.]ýApp#-Gatien of this EAL req ,,rrs u id-etrcp ' g of the actual radjiolgical conditin p r-eep i the ' 4i~4 O,~,f, th n~opit~r, Information N6G NO. 90-08, "KR-85 Hazards from Docye Ful"should be con8ideednetbihn radiatien meniter- EAls.Escalation of this emergency classification level, if appropriate, would be based on AS4-EAL RS1.1 orAG4EAL RG1.1.Explanation/Discussion/Definitions:

Indications of spent fuel damage may include:*Actual visual observation of a fuel handling incident Salem Page 2of 5 Rev. 0(draft E)EAL#: RA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204* Gas bubbles in the vicinity of a fuel bundle* Discoloration of the water in the vicinity of a fuel bundle* Increasing radiation and alarm on area and ventilation radiation monitors When the Spent Fuel Pool (SFP) and refueling cavity are connected, there could exist the possibility of uncovering irradiated fuel. Therefore, this EAL is applicable for conditions in which irradiated fuel is being transferred to and from the Reactor Vessel and SFP.For a loss of shielding, the source of the radiation is within the refueling cavity, refueling canal or SFP. Without the shielding provided by normal water inventory in the SFP, refueling canal and/or refueling cavity, radiation levels from irradiated fuel and activation products will rise substantially in either the Containment or Fuel Handling Building.

Radiation levels > 2 RPhr in the Containment or FHB are indicative of imminent uncovering of spent fuel or reactor internals.

Fuel Handlinq Buildinq (FHB)Area Radiation Monitors (ARMs) 1(2)R5 Spent Fuel, 1(2)R9 New Fuel Storage and 1(2)R32A Fuel Handling Crane are located on the 130' elevation of the FHB.* 1(2)R5 Fuel Handling Bldg -This channel continuously monitors the fuel storage areas.A high radiation alarm will initiate charcoal filtration of the FHB atmosphere.

1(2)R9 Fuel Storage Area -This channel also continuously monitors the fuel storage areas. A high radiation alarm will also initiate charcoal filtration of the FHB atmosphere." 1(2)R32A Fuel Handling Crane Fuel Handling Bldg (local monitor) -This channel is not connected to the central Radiation Monitoring System and is provided with a flashing beacon and stops upward hoist movement.1(2)R41 A Plant Vent is the low range noble gas Plant Vent monitor. Releases of fission product gases to the FHB atmosphere would be transported via the FHB ventilation and detected in the plant vent radiation monitor.Containment Area Radiation Monitor (ARM) 1(2)R2 Containment is located on the 130' elevation of the Containment.

Releases of fission product particulates, iodines or gases to the Containment atmosphere would be transported via Containment ventilation and detected in the Containment Vent Radiation Monitors 1(2)R1 1A (part.), 1(2)R12A (gas) or 1(2)R12B (iodine).Definitions:

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: RA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 VALID -An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed.Implicit in this definition is the need for timely assessment.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AA2 Example EAL #2 2. SI (S2).OP-AB.FUEL-0002(Q)

Loss of Refueling Cavity or Spent Fuel Pool Level 3. SI(S2).OP-AB.RAD-0001(Q)

Abnormal Radiation 4. S1(S2).OP-AB.FUEL-0001(Q)

Fuel Handling Incident 5. UFSAR Section 11.4 Radiation Monitoring Systems Salem Page 4 of 5 Rev. 0 (draft E)EAL#: RA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: RA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-204 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 2 -Onsite Rad Conditions/Fuel Pool Events Damage to irradiated fuel or loss of water level that has resulted or will result in the uncovering of irradiated fuel outside the Reactor Vessel All EAL# & Classification Level: RA2.2 -ALERT EAL: A water level drop in the refueling cavity, spent fuel pool or refueling canal that will result in irradiated fuel becoming uncovered Basis: T[hirSICadd.raeses inrr-,eases in radtiatio"n do-,e rates plant

,'ndr ma'y bea pr.curSor to a te the-These This events represents a loss of control over radioactive material and represents an actual or substantial potential degradation in the level of safety of the plant.[These-This events escalates from AU2-EAL RU2.1 in that fuel activity has-be released, ef is anticipated due to fuel heatup. This IG-EAL applies to spent fuel requiring water coverage and is not intended to address spent fuel which is licensed for dry storage.1 EAL441[Site- speeigie-lindications may include instrumentation such as water level and local area radiation monitors, and personnel (e.g., refueling crew) reports. If available, video cameras may allow remote observation.

Depending on available level instrumentation, the declaration threshold may need to be based on indications of water makeup rate or decrease in water storage tank level.1[In light of ea't-', ,avT" Sea!, fao,., incidents at tw_ differ.ent P. .s and loss of wate.in th ?E Snt Fuel P#2 Fuel Transfer Caa at a B' explicit coverage Of these ty es of e vn S iathresqhold

I is appropri.

ate given the,- p otenta for incrFeased doaces tog plant staff This EAL addresses radiationI monitolr indication1s of fue~l unc~every and/or-, fuel dam~ag-e.Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RA2.2 SGS ECG -EAL Technical Bases EP-SC-111-204 lnrc~ascd ventilation Monitor readings mnay be indication of a radioactivity relcase frmM thc f6ul8, confirming that damage has orreFd. Increased backgeron-d at the veRtilation monitor due to water level decrease may mask inrGeased ventilation exhaust airborne activity and needs to be conRsidered.

While a radiation monitor could detect an inrGeas-e-in dose rate due to a drop in the water level, it might not be a reliable indication of whether Or not the fuel is covered.[For example, a refueling bridge ARM reading may increas due to planned evolutiOns such as head lif, or oven a fuel assembly being raised in the manipulator mast. Also, a monitor co)uld in fact be properly responding to a known event invol'ving transfer or relocato of a source, stored in orF near the fuel pool or responding to a planned evolution such as removal of the r-eactOr head. Generally, inrGeased radiation monitor indications Will need to9 combined with ano~ther indicator (or personnel report) of water loss.]Escalation of this emergency classification level, if appropriate, would be based on AS-1-EAL RS1.1 orMAG4EAL RG1.1.Explanation/Discussion/Definitions:

None EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AA2 Example EAL #1 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RA2.2 SGS ECG -EAL Technical Bases EP-SC-111-204 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RA2.2 SGS ECG -EAL Technical Bases EP-SC-111-205 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

R -Abnormal Rad Levels / Rad Effluent 3 -CR/CAS Rad Rise in radiation levels within the facility that impedes operation of systems required to maintain plant safety functions All EAL# & Classification Level: RA3.1 -ALERT EAL: Basis: This IG-EAL addresses increased radiation levels that- impact continued operation in areas requiring continuous occupancy to maintain safe operation or to perform a safe shutdown.The cause and/or magnitude of the increase in radiation levels is not a concern of this ,GEAL.The Emergency Coordinator must consider the source or cause of the increased radiation levels and determine if any other G-EAL may be involved.T/; /" isno t ,,.t t-o÷ a,.., /, to ;PG~eass the G/ tainnet dome radia tion m n'te " as these are events which are addrFessed in the fission product barrier table.]fhe value of 15mR/hr is derived from the GDC 19 value of 5 rem in 30 days with adjustment for expected occupancy times. Although Section III.D.3 of NUREG-0737, "Clarification of TMI Action Plan Requirements", provides that the 15 mR/hr value can be averaged over the 30 days, the value is used here without averaging, as a 30 day duration implies an event potentially more significant than an Alert.]Areas requiring continuous occupancy include the Control Room and, as appropriate to the-it, any other conRtrolI stations that are staffed continuous~ly, such as, a Ira(dwat conro room,-or a security alarm station. [Typically these areas ar e.the Contrel Room an the Central Alarm Station (CAS).J Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-205 Explanation/Discussion/Definitions:

Control Room ARM 1(2)R1A measures area radiation in a range of 0.1 -10 3 mR/hr. Should increase Control Room radiation be detected, operators are directed to align Control Room Ventilation in the Accident Pressurized mode.There is no permanently installed CAS area radiation monitor that may be used to assess this EAL threshold.

Therefore, this threshold must be assessed via local radiation survey for the CAS.EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, AA3 Example EAL #1 2. UFSAR Section 11.4 Radiation Monitoring Systems 3. S1(S2).OP-AB.RAD-0001(Q)

Abnormal Radiation Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-206 EAL Category:

E -ISFSI EAL Sub-category:

Spent Fuel Transit Initiating Condition:

Damage to a loaded cask CONFINEMENT BOUNDARY Mode Applicability:

Mode NOT applicable EAL# & Classification Level: EU1.1 -UNUSUAL EVENT EAL: Damage to a Multi Purpose Canister (MPC) CONFINEMENT BOUNDARY as indicated by on-contact radiation readings > 600 mR/hr (gamma + neutron) on the surface of the spent fuel cask, excluding the air vents, OR > 60 mR/hr (gamma + neutron) on the top of the spent fuel cask while in transit to the ISFSI.Basis: An N04:E-UNUSUAL EVENT in this ,-0-EAL is categorized on the basis of the occurrence of an event of sufficient magnitude that a loaded in-transit cask-MPC CONFINEMENT BOUNDARY is damaged or violated.

This includes classification based on a loaded fuel storage cask CONFINEMENT BOUNDARY loss leading to the degradation of the ful d-uri aeposing an operational safety problem with respect to its removal from storage.[The of the ISFS! Safet, Apn4,cis Report (SA) per- NURE-G 1536 "r SAR Evaluation Report identify n atural phenomena e'vpts and accident conditionS that coG potentially effect the CONJFINEM4ENT-BOUNDARY-.

This EAL addresses a dropped cock-, a tipped ever c.k, EXPLOSION, PROJEC-TLE damage, FIRE damage or natural emer ffecting a cok (e.g., secevent, torad-Explanation/Discussion/Definitions:

This EAL applies to emergency conditions affecting a spent fuel cask caused by an accident or natural phenomena.

This EAL would be applicable at all times in all modes for a loaded spent fuel storage cask from the time the lid is installed, as the cask leaves the Salem Fuel Handling Building and during transport to the INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI). This EAL provides for an Unusual Event classification, which may be entered if conditions occur that have the potential for damaging or degrading the CONFINEMENT BOUNDARY of a spent fuel cask. Damage to the storage cask could result in an increase in direct radiation readings from the cask. This Salem Page 1 of 3 Rev. 0 (draft E)EAL#: EUI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-206 Salem EAL is only applicable for a Salem spent fuel cask that is in transit to the ISFSI.After the spent fuel cask is in place at the ISFSI, any further conditions that could adversely impact the ISFSI or an individual cask from either Salem or Hope Creek would be assessed and classified as needed by the Hope Creek Shift Manager (SM) per Hope Creek EAL EU1.1.As provided in the Holtec HI-STORM 100 System Certificate of Compliance (CoC), Appendix A (Technical Specifications), Section 5.7.4 contains radiation values for the cask that should not be exceeded.

Under Amendment

5, the highest allowable radiation level on contact with the HI-STORM 100 cask body is 300 mR/hr on the side of the cask and 30 mR/hr on the top of the cask. Keeping in line with NEI guidance that a UE is warranted for radiation conditions at a level of twice the Technical Specification value, 600 mR/hr and 60 mR/hr are being used as the EAL threshold radiation levels.Continued use6of this lower value is conservative for casks loaded under later CoC-amendments where the radiation limit values may increase.

The threshold values-are sufficiently'above nominal radiation levels of the CONFINEMENT BOUNDARYthatýi radiation levels above this EAL threshold would indicate significant damage to the CONFINEMENT BOUNDARY.No releases of radioactive material requiring offsite response or monitoring are expected because the seal-welded spent fuel canister (part of the CONFINEMENT BOUNDARY) is designed to re'main intact under all normal, off-normal, and credible accidenttcoh.-ditidns of onsite transport and storage at the ISFSI, according to Holtec licensing docum-ents.:Prior to the installation of the spent fuel cask lid on the HI-STORM 100 cask, emergency-'--

classifications would be based on other Category R EALs.Definitions:

INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI): A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.CONFINEMENT BOUNDARY:

Is the barrier(s) between areas containing radioactive substances and the environment and includes the multi-purpose canister (MPC) and, for the purposes of this EAL, the associated cask shielding.

EAL Basis Reference(s):

1. NEI 99-01 Rev. 5, E-HU1 Example EAL #1 2. HOLTEC HI-STORM 100 UFSAR, Chapter 5 and Chapter 11 3. Certificate of Compliance, Docket # 72-1014 4. Holtec International Final Safety Analysis Report for the HI-STORM 100 Cask System Holtec Report No.: HI-2002444

5. Certificate of Compliance No. 72-1014 Appendix A Technical Specifications for the HI-STORM 100 Cask System Section 1.1 Definitions Salem Page 2 of 3 Rev. 0 (draft E)EAL#: EU 1.1 SGS ECG -EAL Technical Bases E P-SC- 111 -206 Salem Page 3 of 3 Rev. 0 (draft E)EAL#: EUI.1 EALs for: HAZARD S SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H_- Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting the PROTECTED AREA All EAL# & Classification Level: HUI.1 -UNUSUAL EVENT (Common Site)EAL: Seismic event identified by ANY two of the following: " Earthquake felt in plant by Control Room Operators" SMA-3 Event Indicator (flag) white" National Earthquake Information Center (NEIC) (Note 4)Note 4: The NEIC can be contacted by calling (303) 273-8500.

Select option #1 and inform the analyst you wish to confirm recent seismic activity in the vicinity of Salem/Hope Creek Generating Station. Provide the analyst with the following coordinates:

390 27' 46" (39.4650) north latitude, 750 32' 08" (75.5370) west longitude.

Basis: These-This EALs are-is categorized on the basis of the occurrence of an event of sufficient magnitude to be of concern to plant operators.

EALt-#-Damage may be caused to some portions of the site, but should not affect ability of safety functions to operate.As defined in the EPRI-sponsored Guidelines for Nuclear Plant Response to an Earthquake, dated October 1989, a "felt earthquake" is: An earthquake of sufficient intensity such that: (a)the vibratory ground motion is felt at the nuclear plant site and recognized as an earthquake based on a consensus of control room operators on duty at the time, and (b) for plants with operable seismic instrumentation, the seismic switches of the plant are activated.

Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HU1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207[For mes lps Mt'7 c.sect7isr isrumnaip the7 seisrnqi awitc-h are setL at anp aG lr-ratipfl of about 0. 01g. Thi-s EAL should be developcd op site specific basis. The m~ethod Of detection Gan be based on instrumentation, validated by a roliable &ource, or- Gperater asscssment.]

The National Earthquake Information Center can confirm if an earthquake has occurred in the area of the plant.Explanation/Discussion/Definitions:

SGS seismic instrumentation consists of a Kinemetrics SMA-3 Strong Motion Accelerograph and associated sensors that are equipped with seismic triggers set to alarm (Unit 1 OHA A-37 SEIS RCDR SYS ACT) and initiate recording at an acceleration equal to or exceeding 0.01 g.When the seismic trigger activates the SMA-3 Event Indicator (flag) will change from black to white and the amber event alarm will illuminate.

The amber event alarm will extinguish when ground acceleration reduces below the 0.01 g setpoint but the Event Indicator (flag) will remain white until manually reset. Three time-history triaxial acceleration sensors are provided (2 in Reactor Building, 1 in Auxiliary Building).

These sensors transmit electrical signals to be recorded on magnetic tape.The NEIC can confirm seismic activity in the vicinity of the SGS/HCGS site. Refer to Note 4 to contact the NEIC.Alternatively go to the USGS NEIC website: http.://earth quake. usgs.gov/eqcenter/

On the US map, click on 'New Jersey' and then click on earthquake indicator for information.

The maps are updated within 5 min. of a measured earthquake.

Additional Earthquake information can be found on the internet at:* http://www.earthquake.usgs.gov" http://www.mgs.md.gov (click on "Live Earthquake Data online")" http://earthquake.usgs.gov/regional/neic This event escalates to an ALERT under EAL HA1.1 if the earthquake exceeds Operating Basis Earthquake (OBE) levels (0.1g).An approximate relationship between acceleration units in gravity and magnitude reported per the Richter scale is as follows: An Acceleration of: is approx. equal to a Richter Scale Magnitude of: 0.01g 4.0 0.02g 4.5 Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HU1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 0.lg 0.2g 5.5 6.5 Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HUl.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU1 Example EAL #1 2. UFSAR Table 7.7-3 Seismic Monitoring Instrumentation

3. SC.OP-AB.ZZ-0004(Q)

Earthquake

4. 51.OP-AR.ZZ-0001 (Q) OHA A-37 SEIS RCDR SYS ACT 5. UFSAR 2.1.1 Site Location 6. UFSAR 1.2.4 Seismology Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HUI 1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HU .1 SGS ECG -EAL Technical Bases EP-SC-111-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H__- Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting the PROTECTED AREA All EAL# & Classification Level: HU1.2 -UNUSUAL EVENT (Common Site)EAL: Tornado TOUCHING DOWN within the PROTECTED AREA OR Average Wind Speeds > 95 MPH from ANY elevation of the Met Tower Basis: These-This EALe are-is categorized on the basis of the occurrence of an event of sufficient magnitude to be of concern to plant operators.

E-AL-#2 This EAL is based on a tornado striking (touching down) within the PROTECTED AREA or high winds onsite within the Protected Area.fThe hitqh wind,1 valueh shniIH hbe h~e nn e5fi FSA dSinn hbasi asrn Ro it is within the ranGe of the inStrum~entation available for wind soeed.]Escalation of this emergency classification level, if appropriate, would be based on VISIBLE DAMAGE-DEGRADED PERFORMANCE, or by other iý-in-plant conditions, via EAL HA1.2.Explanation/Discussion/Definitions:

Average, as used in the EAL threshold, is intended to be the 15 minute rolling average as provided by SPDS and not the instantaneous wind speed.The design wind velocities are 108 mph (including a gust factor of approximately 1.3) at 30 feet above ground. However, the Control Room wind speed only provides indication up to 100 mph so the classification threshold has been capped at 95 mph to allow for onscale indication of wind speed. The manner in which the HCGS SPDS processes data from the meteorological Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HU 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 instrumentation differs from the SGS SPDS; consequently, minor differences between HCGS and SGS readings may occur.A tornado touching down within the PROTECTED AREA warrants declaration of an UNUSUAL EVENT regardless of the measured wind speed at the meteorological tower. A tornado is defined as a violently rotating column of air in contact with the ground and extending from the base of a thunderstorm.

The National Weather Service can be contacted for further information about existing or projected Adverse Weather Conditions:

Phila/Mount Holly (609) 261-6600* NWS Web site http://www.erh.noaa.gov/er/phi" Phila/Mount Holly (609) 261-6604 , Phila/Mount Holly (609) 261-6602 Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.VISIBLE DAMAGE: Damage to equipment or structure that is readily observable without measurements, testing, or analysis.

Damage is sufficient to cause concern regarding the continued operability or reliability of the affected structure, system, or component.

Example damage includes:

deformation due to heat or impact, denting, penetration, rupture, cracking, and paint blistering.

Surface blemishes (e.g., paint chipping, scratches) should not be included.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU1 Example EAL #2 2. UFSAR 3.3.1.1 Design wind Velocity and Loading 3. OP-AA-108-111-1001 Severe Weather and Natural Disaster Guidelines

4. NC.CH-SC.MET-1206(Q)

Meteorological Monitoring System Calibration and Maintenance

5. SC.OP-AB.ZZ-0001(Q)

Adverse EnIvironmental Conditions Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HU 1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G--H_- Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting the PROTECTED AREA All EAL# & Classification Level: HUl.3 -UNUSUAL EVENT EAL: Main Turbine rotating component failures resulting in EITHER of the following: " Main Turbine casing penetration

Main Turbine or Generator Seal Damage Basis: These-This EALs are-is categorized on the basis of the occurrence of an event of sufficient magnitude to be of concern to plant operators.

E-AL-#4 This EAL addresses main turbine rotating component failures of sufficient magnitude to cause observable damage to the turbine casing or to the seals of the turbine generator.

Generator seal damage observed after generator purge does not meet the intent of this EAL because it did not impact normal operation of the plant.Of major concern is the potential for leakage of combustible fluids (lubricating oils) and gases (hydrogen cooling) to the plant environs.

Actual fires and flammable gas build up are appropriately classified via EAL HU2.1 and EAL HU3.1.This EAL is consistent with the definition of an UNUSUAL EVENT NOUE while maintaining the anticipatory nature desired and recognizing the risk to non-safety related equipment.

Escalation of this emergency classification level, if appropriate, would be to EAL HA1.3 based on damage done by projectiles generated by the failure or by pythe radiological releases in Category R. for a 3W\, or in conjn ction with a steam generator tube rupture, for a PWR.Th.i'sn !1tff r .zvtznf. woul.d ho c s 1f1-,i hy tho. r.-'idpnnirAl

!Cq nr Pisqinn Prntr, f Rprripr [Ci Explanation/DiscussionlDefinitions:

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HU1.3 SGS ECG -EAL Technical Bases EP-SC-111-207 Main Turbine rotating component failures of sufficient magnitude to cause damage to the turbine casing or turbine/generator seals increases the potential for leakage of combustible/explosive gases and of combustible liquids to the Turbine Building or damage to plant systems due to PROJECTILES.

The presence of H 2 gas in sufficient quantities may present a combustion hazard. Actual fires and flammable gas build up is classified under fire and flammable gas EALs.Generator seal damage observed after generator purge does not meet the intent of this EAL since it did not impact normal plant operations.

Turbine rotating component failures may also result in other direct damage to plant systems and components.

Damage may rupture the turbine lubricating oil system, which would release flammable liquids to the Turbine Building.

Potential rupture of the condenser and condenser tubes may cause flooding in the lower levels of the Turbine Building.

This damage should be readily observable.

Escape of H 2 gas from the generator due to a loss of seal oil pumps or turbine lube oil without a turbine rotating component failure should not be classified under this event but should be reviewed lAW EALs in Subcategory H.3, Hazardous Gas.Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability or personnel safety.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU1 Example EAL #4 2. UFSAR 3.5.4 Turbine Missile Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HU1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting the PROTECTED AREA All HUI.4- UNUSUAL EVENT Internal Flooding that has the potential to affect safe shutdown systems or components required by Technical Specifications for the current operating mode in ANY Table H-1 plant structure Table H-1 Plant Structures Containing Safe Shutdown Systems or Components

Auxiliary Building* Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas* Containment

Fuel Handling Building* Service Building* RWST, PWST, and AFWST Area Basis: These-This EALs are-is categorized on the basis of the occurrence of an event of sufficient magnitude to be of concern to plant operators.

This EAL addresses the effect of internal flooding caused by events such as component failures, equipment misalignment, or outage activity mishaps.Salem Page 1 of 4 Rev. 0 (draft E)EAL#: H U 1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207[The- sit spcfceaS inr.IIGde those areas. that con tain sytm require~d Afp safe 6' wn oR-G the plan,, which are not designed to be partia#ly or fuly submer.ged.

.The /PEEEE may proevide insight in to areas to be con cidered when developing this AL.]Escalation of this emergency classification level, if appropriate, would be based DAMAG-E~on DEGRADED PERFORMANCE via EAL HA1.4, or by other plant conditions.

Explanation/Discussion/Definitions:

Flooding as used in this EAL describes a condition where water is entering the room faster than installed equipment is capable of removal, resulting in a rise of water level within the room. Classification of this EAL should not be delayed while corrective actions are being taken to isolate the water source.The Table H-1 Plant Structures Containing Safe Shutdown Systems or Components include those plant structures identified as Seismic Category I.Flooding can occur from several sources including the Circulating Water System, Service Water System, Demineralized Water, Component Cooling Water, Fire Protection and Refueling Water Storage Tank.Flooding is determined in these areas by visual report from staff or by confirmation of sump alarms. SI(S2).OP-AB.ZZ-0002 (Q) directs the operators to determine the exact location and severity of flooding.

Attachments in this procedure delineate the affected plant areas, potential source(s) of water, affected vital equipment, flood rate and time to submerge vital equipment.

If mitigating actions to control flooding have been unsuccessful and the flooding level has reached 50% of the equipment disabled level(s) as specified in S1(S2).OP-AB.ZZ-0002, FLOODING, then the flooding is severe, is in excess of sump handling capability and has the potential to affect safety equipment and therefore, classification under this EAL is warranted.

The source of the flooding and the status of the sump pumps are not factors in evaluating this EAL. For areas that do not have a flooding level specified in SI(S2).OP-AB.ZZ-0002, SM judgment should be used.Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 2 of 4 Rev. 0 (draft E)EAL#: HU 1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207 DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability:

Electrical faults on power supplies" Normally closed breakers in tripped position* System annunciators activated" System warning lights lit" Insufficient system pressure from keep-fill pumps" Elevated area temperatures or radiation levels* Increased sump pump operation in areas in which the system is located EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU1 Example EAL #3 2. UFSAR 3.2 Classification of Structures, Components and Systems 3. S1(S2).OP-AB.ZZ-0002 (Q) Flooding Salem Page 3 of 4 Rev. 0 (draft E)EAL#: HU 1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: HU 1.4 SGS ECG -EAL Technical Bases EP-SC-11 11-207 EAL Category:

C -Hazards & Other Conditions Affecting Plant Safety EAL Subcategory:

1 -Natural & Destructive Phenomena Initiating Condition:

Natural or destructive phenomena affecting the PROTECTED AREA Mode Applicability:

All EAL# & Classification Level: HU1.5 -UNUSUAL EVENT (Common Site)EAL: River level > 99.5'OR River level < 80.0'Basis: This addresses other s6e specific phenomena (such as hurricane, flood, 9r s.iche) that .an also be precursors of more serious events.See Explanation Section below: Explanation/Discussion/Definitions:

The first condition of this EAL indicates river level conditions that can threaten the level of safety of the plant due to flooding.

River level greater than 99.5' (+10.5' Mean Sea Level, MSL) is indication of impending site flood conditions.

Flood protection measures are required by Salem Technical Specifications and procedure at 99.5'(+10.5'MSL).

At this river level precautionary actions are taken, including filling outside tanks and ensuring that perimeter flood doors are closed. These actions ensure that the facility flood protection features are in place prior to a river level that would necessitate their use. Hope Creek performs these actions at 95.0' (+6.0'MSL).

The High river level threshold is below the river level that would require a plant shutdown.Technical Specification actions required by a River Level of >100.5' includes placing the plant in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .This is based on the river level at which facility flood protection features provide protection to safety related equipment.

Hope Creek performs similar actions are at 99.5' (+10.5'MSL).

The grade level at the Salem station is lower than that for Hope Creek (Salem = 99.5', Hope Creek = 101.5').Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HU1.5 SGS ECG -EAL Technical Bases EP-SC-1 11-207 The second condition of this EAL indicates river level conditions, River level < 80.0'(-9.0'MSL), approaching the loss of the Service Water Intake (Ultimate Heat Sink). The low level threshold indicates a river level condition that is one foot lower than the historical low water level of 81.0' (-8.0'MSL) (December 31, 1962) and is higher than the Service Water pumps design level.These events will be escalated based on damage to plant safety systems, loss of fission product barriers or abnormal radiological releases as discussed in other EAL categories.

River level indication is displayed in Unit 1 on LA-8639 which has a range of 70' to 110'.The National Weather Service can be contacted for further information about existing or projected Adverse Weather Conditions:

Phila/Mount Holly (609) 261-6600" NWS Web site http://www.erh.noaa.-gov/er/phi

Phila/Mount Holly (609) 261-6604" Phila/Mount Holly (609) 261-6602 Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU1 Example EAL #5 2. Technical Specifications 3/4.7.5 Flood Protection

3. UFSAR 2.4 Hydraulic Engineering

4. UFSAR Figure 2.4-3 Service Water Intake 5. UFSAR Figure 3.4-1 Datum and Water Level Relationships

6. S1(S2).OP-AB.CW-0001(Q)

Circulating Water System Malfunction

7. S1 (S2).OP-AB.ZZ-0002(Q)

Flooding 8. OP-AA-1 08-111-1001 Severe Weather and National Disaster Guidelines Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HU 1.5 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting VITAL AREAS All HAl.1 -ALERT Actuation of the Hope Creek OBE Seismic Switch (> 0.1g) has occurred as verified by the Hope Creek Shift Manager AND Earthquake confirmed by ANY of the following:

Earthquake felt in plant by Control Room Operators" National Earthquake Information Center (NEIC) (Note 4)" Control Room indication of DEGRADED PERFORMANCE of safe shutdown systems Note 4: The NEIC can be contacted by calling (303) 273-8500.

Select option #1 and inform the analyst you wish to confirm recent seismic activity in the vicinity of Salem/Hope Creek Generating Station. Provide the analyst with the following coordinates:

390 27' 46" (39.4650) north latitude, 750 32' 08" (75.5370) west longitude.

Basis: These-This EALs escalates from HUI .1 in that the occurrence of the event has-may have resulted in damage to plant structures or areas containing equipment necessary for a safe shutdown, or has-may have caused damage to the safety systems in those structures evidenced by Ceontrol R-oom indications of degraded system response or performance.

The occurrence of visible-damage and/or degraded system response is intended to discriminate against lesser events. The initial report should not be interpreted as mandating a lengthy damage assessment prior to classification.

No attempt is made in this EAL to assess the actual magnitude of the damage. The significance here is not that a particular system or structure was damaged, but rather, that the event was of sufficient magnitude to cause this degradation.

Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 Escalation of this emergency classification level, if appropriate, would be based on System Malfunction 1rsEALs.EALs # #5 ,These -EA-1s Shouldl specify, site speifiG Structures or- areas that contain Safety system, o0 cOMPonent and functions re quIrc d for- safe shutdown of the plant. Site &peccifiGQSafe htdw A na4ysis should be Gonsulted for equipment and plan ta ~ara r-qiI% to establish or-miti EAL-#1 Seismic events of this magnitude can result in a VITAL AREA being subjected to forces beyond design limits, and thus damage may be assumed to have occurred to plant safety systems.[This thresholdl should be basee don Site Specific F&SA de sign basis. Se E I-POl pono"Guidplines for uler Plant Response to an EaFh quake"L, dated October- 19891, fo;6 The National Earthquake Information Center can confirm if an earthquake has occurred in the area of the plant.Explanation/Discussion/Definitions:

Ground motion acceleration of 0.1g is the Operating Basis Earthquake (OBE) for SGS.As defined in the EPRI-sponsored Guidelines for Nuclear Plant Response to an Earthquake, dated October 1989, a "felt earthquake" is: An earthquake of sufficient intensity such that: (a)the vibratory ground motion is felt at the nuclear plant site and recognized as an earthquake based on a consensus of Control Room operators on duty at the time, and (b) for plants with operable seismic instrumentation, the seismic switches of the plant are activated.

The NEIC can confirm seismic activity in the vicinity of the SGS/HCGS site. Refer to Note 4 to contact the NEIC.Alternatively go to the USGS NEIC website: http.://earthquake.

usgs.gov/eqcenter!

On the US map, click on 'New Jersey' and then click on earthquake indicator for information.

The maps are updated within 5 min. of a measured earthquake.

Additional Earthquake information can be found on the internet at: http://www.earthquake.usgs.gov Salem Page 2of 5 Rev. 0(draft E)EAL#: HAl-SGS ECG -EAL Technical Bases EP-SC-1 11-207* http://www.mgs.md.gov (click on "Live Earthquake Data online")* http://earthquake.usgs.gov/regional/neic An approximate relationship between acceleration units in gravity and magnitude reported per the Richter scale is as follows: An Acceleration of: is approx. equal to a Richter Scale Magnitude of: 0.01g 4.0 0.02g 4.5 0.1 g 5.5 0.2g 6.5 Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability: " Electrical faults on power supplies" Normally closed breakers in tripped position* System annunciators activated* System warning lights lit" Insufficient system pressure from keep-fill pumps* Elevated area temperatures or radiation levels" Increased sump pump operation in areas in which the system is located PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center. I Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HAl.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA1 Example EAL #1 2. UFSAR Table 7.7-3 Seismic Monitoring Instrumentation

3. SC.OP-AB.ZZ-0004(Q)

Earthquake

4. S1.OP-AR.ZZ-0001 (Q) OHA A-37 SEIS RCDR SYS ACT 5. UFSAR 2.1.1 Site Location 6. UFSAR 1.2.4 Seismology Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category:

C -Hazards & Other Conditions Affecting Plant Safety EAL Subcategory:

1 -Natural & Destructive Phenomena Initiating Condition:

Natural or destructive phenomena affecting VITAL AREAS Mode Applicability:

All EAL# & Classification Level: HA1.2 -ALERT EAL: Tornado TOUCHING DOWN within the PROTECTED AREA OR Average Wind Speeds > 95 MPH from ANY elevation of the Met Tower AND Resulting in EITHER of the following:

Control Room indication of DEGRADED PERFORMANCE of a Safety System* VISIBLE DAMAGE to ANY of the plant structures in Table H-1 Table H-1 Plant Structures Containing Safe Shutdown Systems or Components

Auxiliary Building 0 Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas 0 Containment 0 Fuel Handling Building* Service Building o RWST, PWST, and AFWST Area Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 Basis: This EAL escalates from EAL HU1.2 in that the occurrence of the event has resulted in VISIBLE DAMAGE to plant structures or areas containing equipment necessary for a safe shutdown, or has caused damage to the safety systems in those structures evidenced by Coontrol Rfoom indications of degraded system response or performance.

The occurrence of VISIBLE DAMAGE and/or degraded system response is intended to discriminate against lesser events. The initial report should not be interpreted as mandating a lengthy damage assessment prior to classification.

No attempt is made in this EAL to assess the actual magnitude of the damage. The significance here is not that a particular system or structure was damaged, but rather, that the event was of sufficient magnitude to cause this degradation.

Escalation of this emergency classification level, if appropriate, would be based on System Malfunction 42,sEALs.EALs #2 #5[Those EALs should sp e ify site &pe'fic str-UG4re ero orea pp that contain safet sy4stem,-Gor GO..9omPoent and functions requir-e dfor safe shutdown3 of the plant. Site spoelific Safe ShutdownýAnal-s.eS should be consult ed for equipment and plant areas required to estabgsh or- maintaih E-AL-#2-This EAL is based on a tornado .tri,-', (touching down) or high winds that have caused VISIBLE DAMAGE to structures containing functions or systems required for safe shutdown of the plant.Explanation/Discussion/Definitions:

Average, as used in the EAL threshold, is intended to be the 15 minute rolling average as provided by SPDS and not the instantaneous wind speed.The design wind velocities are 108 mph (including a gust factor of approximately 1.3) at 30 feet above ground. However, the Control Room wind speed only provides a display up to 100 mph so the classification threshold has been capped at 95 mph to allow for onscale indication of wind speed. The manner in which the HCGS SPDS processes data from the meteorological instrumentation differs from the SGS SPDS; consequently, minor differences between HCGS and SGS readings may occur.The ALERT classification is appropriate if relevant plant parameters indicate that the performance of safety systems has been degraded.

No attempt should be made to fully inventory the actual magnitude of the damage or quantify the degradation of safety system performance prior to declaration of an ALERT under this threshold.

The declaration of an ALERT and the activation of the TSC provide the Emergency Coordinator with the resources needed to perform detailed damage assessments.

Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 The National Weather Service can be contacted for further information about existing or projected Adverse Weather Conditions: " Phila/Mount Holly (609) 261-6600* NWS Web site http://www.erh.noaa.gov/er/phi

Phila/Mount Holly (609) 261-6604* Phila/Mount Holly (609) 261-6602 Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability:

Electrical faults on power supplies* Normally closed breakers in tripped position* System annunciators activated* System warning lights lit* Insufficient system pressure from keep-fill pumps" Elevated area temperatures or radiation levels* Increased sump pump operation in areas in which the system is located PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 VISIBLE DAMAGE: Damage to equipment or structure that is readily observable without measurements, testing, or analysis.

Damage is sufficient to cause concern regarding the continued operability or reliability of the affected structure, system, or component.

Example damage includes:

deformation due to heat or impact, denting, penetration, rupture, cracking, and paint blistering.

Surface blemishes (e.g., paint chipping, scratches) should not be included.Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HAI Example EAL #2 2. UFSAR 3.3.1.1 Design wind Velocity and Loading 3. UFSAR 3.2 Severe Weather and Natural Disaster Guidelines

4. OP-AA-1 08-111-1001 Severe Weather and Natural Disaster Guidelines

5. NC.CH-SC.MET-1206(Q)

Meteorological Monitoring System Calibration and Maintenance

6. SC.OP-AB.ZZ-0001(Q)

Adverse Environmental Conditions Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA1.2 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting VITAL AREAS All HAI.3 -ALERT Turbine failure-generated PROJECTILES resulting in EITHER of the following:

VISIBLE DAMAGE to ANY Table H-1 plant structures

Control Room indication of DEGRADED PERFORMANCE of safe shutdown systems Table H-1 Plant Structures Containing Safe Shutdown Systems or Components

Auxiliary Building* Service Water Intake Structure" Control Point Area* Inner/Outer Penetration Areas* Containment

Fuel Handling Building* Service Building* RWST, PWST, and AFWST Area Basis: These-This EALs escalates from EAL HU1.3 in that the occurrence of the event has resulted in VISIBLE DAMAGE to plant structures or areas containing equipment necessary for a safe shutdown, or has caused damage to the safety systems in those structures evidenced by Coontrol Rfoom indications of degraded system response or performance.

The occurrence of VISIBLE DAMAGE and/or degraded system response is intended to discriminate against lesser events. The initial report should not be interpreted as mandating a lengthy damage assessment prior to classification.

No attempt is made in this EAL to assess the actual Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA1.3 SGS ECG -EAL Technical Bases EP-SC-111-207 magnitude of the damage. The significance here is not that a particular system or structure was damaged, but rather, that the event was of sufficient magnitude to cause this degradation.

Escalation of this emergency classification level, if appropriate, would be based on System Malfunction ,L;-sEALs.

EALs #2 -5[These EA4Ls shouldspeir, sA'S Ij t~ite &he~ific-str'~e ortr- apreas that contain safcty sycten,--mGo cOMPOnent andl funG9P etonequir-ed for- safe shutdown of the plant. Site sp ecifiG Safe Shutdown ol d, be .onsulted for m-t end.p.. areas req.i to establish or mait This EAL addresses the threat to safety related equipment imposed by PROJECTILES generated by main turbine rotating component failures.

Therefore, this EAL is consistent with the definition of an ALERT in that the potential exists for actual or substantial potential degradation of the level of safety of the plant.Explanation/Discussion/Definitions:

Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability:

o Electrical faults on power supplies* Normally closed breakers in tripped position* System annunciators activated* System warning lights lit" Insufficient system pressure from keep-fill pumps Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-207" Elevated area temperatures or radiation levels" Increased sump pump operation in areas in which the system is located Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HA1.3 SGS ECG -EAL Technical Bases EP-SC-111-207 PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.VISIBLE DAMAGE: Damage to equipment or structure that is readily observable without measurements, testing, or analysis.

Damage is sufficient to cause concern regarding the continued operability or reliability of the affected structure, system, or component.

Example damage includes:

deformation due to heat or impact, denting, penetration, rupture, cracking, and paint blistering.

Surface blemishes (e.g., paint chipping, scratches) should not be included.PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability or personnel safety.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA1 Example EAL #4 2. UFSAR 3.5.4 Turbine Missiles Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-207 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA1.3 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting VITAL AREAS All HA1.4 -ALERT Internal Flooding in ANY Table H-1 plant structure AND The Flooding is of a magnitude that results in EITHER of the following: " Indication of DEGRADED PERFORMANCE of a Safety System within a Table H-1 Structure.

An Industrial Safety Hazard (Electrical Shock, High Temp, etc.) resulting in access restrictions to operate or monitor Safety System equipment.

Table H-1 Plant Structures Containing Safe Shutdown Systems or Components

Auxiliary Building* Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas* Containment

Fuel Handling Building* Service Building* RWST, PWST, and AFWST Area Basis: These-This EALs escalates from EAL HU1.4 in that the occurrence of the event has resulted in VISIBLE DAMAGE to plant Structur.es or areas con.taining equipme,,t for a safee Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA1.4 SGS ECG -EAL Technical Bases EP-SC-111-207 shutdoWn, or has caus.. an electrical shock hazard precluding access to plant structures containing safe shutdown systems or components or damage to the safety systems or components in those structures as evidenced by Ceontrol Rfoom indications of degraded system response or performance.

The lack of access or occurrence of VISIBLE DDAMAGE an4ier degraded system response is intended to discriminate against lesser events. The initial report should not be interpreted as mandating a lengthy damage-assessment prior to classification.

No attempt is made in this EAL to assess the actual magnitude of t-he-any damage. The significance here is not that a particular system or structure was damaged, but rather, that the event was of sufficient magnitude to cause this lack of access or performance degradation.

Escalation of this emergency classification level, if appropriate, would be based on System Malfunction IsEALs.EALs #2 -#5[These EALs should sri,,. t , p ,.fi- o÷t,,,.÷, or areas that .GRtaon system. , or compnentand fun ction Feuie r o safe shutdown3 of the plant. Site spa c/fic Sa oSudw be con.sulted for- equipment and plant areas required to establsh or maintain This EAL addresses the effect of internal flooding caused by events such as component failures, equipment misalignment, or outage activity mishaps. It is based on the DEGRADED PERFORMANCE of systems, or has created industrial safety hazards (e.g., electrical shock)that preclude necessary access to operate or monitor safety equipment.

The inability to access, operate or monitor safety equipment represents an actual or substantial potential degradation of the level of safety of the plant.Flooding as used in this EAL describes a condition where water is entering the room faster than installed equipment is capable of removal, resulting in a rise of water level within the room. Classification of this EAL should not be delayed while corrective actions are being taken to isolate the water source.Explanation/Discussion/Definitions:

Flooding is an event or condition in excess of the available sump pump handling capability (installed or temporary) that results in a condition where water is entering a room faster than it is being removed resulting in a rise in water level within the room. Classification should not be delayed while taking corrective actions to isolate the source of the flooding.

This EAL addresses the effects of flooding caused by events such as component failures, equipment misalignment, or outage activity mishaps where flooding is occurring in areas that affect safety related equipment.

This EAL is based on the degraded performance of systems, or has created industrial safety hazards (electrical shock) that preclude necessary access to operate or monitor safety equipment.

The inability to access, operate or monitor safety equipment Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HA1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207 represents an actual or substantial potential degradation of the level of safety of the plant meeting the definition of an ALERT.In those cases where it is believed that DEGRADED PERFORMANCE due to flooding may have caused damage to a Safety System, an ALERT declaration is warranted since the full extent of the damage need not be known. A Safety System is defined as any system required to maintain safe operation or to establish or maintain Cold Shutdown.If the flooding has reached the level(s) specified in OP-AB.ZZ-0002, FLOODING, then the flooding is severe, is in excess of sump handling capability and has degraded the performance of safety related equipment.

Consequently, if the flooding has reached the levels specified in OP-AB.ZZ-0002, Flooding, then classification under this EAL is warranted.

The source of the flooding and the status of the sump pumps are not factors in evaluating this EAL. For areas that do not have a Flooding level specified in OP-AB.ZZ-0002, SM judgment should be used.Flooding is determined in these areas by visual report from staff or by confirmation of sump alarms. S1 (S2).OP-AB.ZZ-0002 (Q) directs the operators to determine the exact location and severity of Flooding.

Attachments in this procedure delineate the affected plant areas, potential source(s) of water, affected vital equipment, flood rate and time to submerge vital equipment.

Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability:

Electrical faults on power supplies* Normally closed breakers in tripped position* System annunciators activated* System warning lights lit* Insufficient system pressure from keep-fill pumps Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HA1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207" Elevated area temperatures or radiation levels" Increased sump pump operation in areas in which the system is located Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207 PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA1 Example EAL #3 2. UFSAR 3.2 Classification of Structures, Components and Systems 3. Sl(S2).OP-AB.ZZ-0002 (Q) Flooding Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA1.4 SGS ECG -EAL Technical Bases EP-SC-1 11-207 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Hazards & Other Conditions Affecting Plant Safety 1 -Natural & Destructive Phenomena Natural or destructive phenomena affecting VITAL AREAS All HA1.6 -ALERT Vehicle Crash or PROJECTILE Impact with or within ANY Table H-1 Structure AND The Vehicle Crash or PROJECTILE Impact results in EITHER of the following: " Control Room indication of DEGRADED PERFORMANCE of a Safety System within Table H-1 Structure" VISIBLE DAMAGE to ANY of the plant structures in Table H-1 Table H-1 Plant Structures Containing Safe Shutdown Systems or Components" Auxiliary Building" Service Water Intake Structure" Control Point Area* Inner/Outer Penetration Areas" Containment" Fuel Handling Building* Service Building* RWST, PWST, and AFWST Area Basis: These EALs escalate from HUI in that the occurrence of the eVent has resulted in VISIBLE-DAMAGE to plant structures or areas conRtaRinig equ~ipment necessary fo~r a safe shutdoWn, o9 has caused damacie to the safety systems in those str-ructu-res6 evidenced byý conRtrol room J d Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA1.6 SGS ECG -EAL Technical Bases EP-SC-1 11-207 indications of degraded system responSe or pe..orma..

.The occurrence of VISIBLE DAMAGE and/or degraded system response is intended to discriminate against lesser events.The initial report should not be interpreted as mandating a lengthy damage assessment prior to classification.

No attempt is made in this EAL to assess the actual magnitude of the damage. The significance here is not that a particular system or structure incurred damage, but rather that the event was of sufficient magnitude to cause either VISIBLE DAMAGE to the safety systems in Table H-1 structures or Control Room indications of degraded system performance.The[MCD1]

sigRificance herc is that a paoticular system Fsruture was damaged, but rather, that the event was of sufficient m.agnitGud to cause this degradation.

Escalation of this emergency classification level, if appropriate, would be based on EALs in Category S, System Malfunctionsits.

EALsf#2 #5 r -A.os E-Aka should apecify site specific atutur' or --Lh -e aiP 6649 41 Y-aytemý--OF trau cress should or consulednf qu ntaining tndant and srys required tof d e tor safet n structures, systems, or components containing functions and systems required for safe shutdown of the plant.Explanation/Discussion/Definitions:

The primary concern in this EAL is the magnitude of the vehicle crashes/ PROJECTILE impacts. A detailed assessment of system damage is not required prior to classification.

Vehicle Crash includes AIRCRAFT, Helicopters, Ships, Barges, Trucks, Autos, or any other vehicle types of sufficient momentum to potentially damage the structure.

Minor contacts (not crashes) by onsite vehicles such as trucks, autos, forklifts, etc., are excluded from classification under this EAL. PROJECTILE impact includes flying objects from either offsite or onsite, rotating equipment or turbine failure causing turbine-casing penetration.

A Safety System is any system required to maintain safe operation or to establish or maintain cold shutdown.

In those cases where it is believed that the vehicle crash/ PROJECTILE impact may have caused VISIBLE DAMAGE to a Safety System, an ALERT declaration is warranted since the full extent of the damage may not be known. The turbine building is not a safety structure and would not be considered for this EAL.No lengthy or time-consuming assessment of damage is required prior to classification.

In this EAL, no attempt is made to quantify the magnitude of the damage to any safety system but Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HA1.6 SGS ECG -EAL Technical Bases EP-SC-1 11-207 instead an attempt is made to identify any damage in order to quantify the magnitude and extent of the vehicle crashes/PROJECTILE impact.In short, if the vehicle crash/ PROJECTILE impact is big enough that it has damaged a Safety System/Safety Structure or cause Safety System DEGRADED PERFORMANCE, then the vehicle crash/ PROJECTILE impact is big enough to justify an ALERT declaration.

Any security aspects or suspected HOSTILE ACTIONS that involve vehicles or PROJECTILE impact should be considered under EALs in Subcategory H.4.This event will be escalated based on further damage to plant safety systems, fission product barriers, or abnormal radiation releases.

The Emergency Coordinator may use discretion and escalate the classification to a SITE AREA EMERGENCY based on the nature of the damage.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HA1.6 SGS ECG -EAL Technical Bases EP-SC-1 11-207 Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability, or personnel safety.DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability: " Electrical faults on power supplies* Normally closed breakers in tripped position* System annunciators activated* System warning lights lit* Insufficient system pressure from keep-fill pumps* Elevated area temperatures or radiation levels" Increased sump pump operation in areas in which the system is located PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA1.6 SGS ECG -EAL Technical Bases EP-SC-1 11-207 VISIBLE DAMAGE: Damage to equipment or structure that is readily observable without measurements, testing, or analysis.

Damage is sufficient to cause concern regarding the continued operability or reliability of the affected structure, system, or component.

Example damage includes:

deformation due to heat or impact, denting, penetration, rupture, cracking, and paint blistering.

Surface blemishes (e.g., paint chipping, scratches) should not be included.AIRCRAFT:

Includes both small and large AIRCRAFT.

Examples of AIRCRAFT include general aviation Cessna, Piper and Lear type private planes, large passenger or freight planes as well as police, medical and media helicopters.

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate PSEG to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OCA).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA1 Example EAL #5 2. UFSAR 3.2 Classification of Structures, Components and Systems Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA1.6 SGS ECG -EAL Technical Bases EP-SC-11 11-208 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H_- Hazards & Other Conditions Affecting Plant Safety 2 -Fire or Explosion FIRE within the PROTECTED AREA not extinguished within 15 minutes of detection or EXPLOSION within the PROTECTED AREA All EAL# & Classification Level: HU2.1 -UNUSUAL EVENT EAL: FIRE NOT extinguished within 15 minutes of EITHER of the following: " Control Room notification/report of a FIRE* Verified FIRE detection system alarm/actuation AND FIRE is located in the Turbine Building or ANY Table H-1 plant structure (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Table H-1 Plant Structures Containing Safe Shutdown Systems or Components

Auxiliary Building" Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas* Containment" Fuel Handling Building" Service Building" RWST, PWST, and AFWST Area Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 Basis: This EAL addresses the magnitude and extent of FIRES or EXPLOSIONS that may be potentially significant precursors of damage to safety systems. It addresses the FIRE-4 EXPLOSION, and not the degradation in performance of affected systems that may result.As used h-ere, detection is visua p b serF'atien and report by plant pcrsonne!

orF sensor alarm The 1 5 minute time period begins with a crcdible notification that a FIRE is occu-rringJ, Or indication of a FIRE detection systc m alarm/actuation.

Verification of a FIRE detection system alarm/actuation includes actionRs that can be takenl within the contro~l roomn or other nearby site specific location to ensure that it is not spurious.

An alarm; i's assumed to be an indication of a FIRE Unl Css it is dispro'd wi~thiR the 15 m~inute period by personnel dispatched to the scene.In other words, a personnel report from the scene may be used to disprove a sensor alarmA it received within 1 5 minutes of the ala"rm, but shall not be required to verify the alarm.The 15 minute time period begins with a credible notification/report that a FIRE is occurring, or upon verification that a FIRE detection system alarm/actuation is due to a FIRE.a. A credible notification/report to the Control room would be a communications from a member of the plant staff (in-house or contractor) that identifies the observation of a FIRE in a specific location.NOTE: In this case, the 15 minute clock to assess the EAL and to extinguish the FIRE runs concurrently and starts upon Control Room receipt of the FIRE notification/report.

b. Verification that a FIRE detection system alarm/actuation is due to a FIRE (not a spurious/false alarm) includes either one of the following:

1. Control Room (or other nearby site-specific location) receipt of related independent alarm(s) (FIRE, temperature, deluge, FIRE pump start, etc.)NOTE: In this case, the 15 minute clock to assess the EAL and to extinquish the FIRE runs concurrently and starts upon receipt of the independent alarm(s) related to the FIRE.2. On/Near-scene visual confirmation if only a single FIRE/smoke detector has alarmed.NOTE: In this case, the 15 minute clock to assess the EAL and to extinguish the FIRE runs concurrently and starts upon an on/near-scene confirmation of a FIRE related to the single FIRE/smoke detector that had alarmed.Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 The intent of this 15 minute duration is to size the FIRE and to discriminate against small FIRES that are readily extinguished (e.g., smoldering waste paper basket).IThe Site SpeeifieTurbine Building and Table H-1 list should beis limited and applies to buildings and areas in actual contact with or immediately adjacent to VITAL AREAS or other significant buildings or areas. The intent of this IG-EAL is not to include buildings (i.e., warehouses) or areas that are not in actual contact with or immediately adjacent to VITAL AREAS. This excludes FIRES within administration buildings, waste-basket FIRES, and other small FIRES of no safety consequence.

Immediately adjacent implies that the area immediately adjacent contains or may contain equipment or cabling that could impact equipment located in VITAL AREAS or the FIRE could damage equipment inside VITAL AREAS or that precludes access to VITAL AREAS.]EAL#21 This _EAL adrse ol hsEPOIN o ufcent force to damnag prmanent stru'tu"e-orF equimen w .. the PROTECTED AREA.No attempt is made to assess the actual magnitude of the damnage. The occGurrence of the EXPLOSION is t for declaration,.

The .

.-..........

e eed.t...nsd.er any security asPt-s- of the EXPLOSlON, if appliable.

Escalation of this emergency classification level, if appropriate, would be based on EAL HA2.1.Explanation/Discussion/Definitions:

The Table H-1 Plant Structures Containing Safe Shutdown Systems or Components include those plant structures identified as Seismic Category I.Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU2 Example EAL #1 2. UFSAR 3.2 Classification of Structures, Components and Systems Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H_- Hazards & Other Conditions Affecting Plant Safety 2 -Fire or Explosion FIRE within the PROTECTED AREA not extinguished within 15 minutes of detection or EXPLOSION within the PROTECTED AREA All EAL# & Classification Level: HU2.2 -UNUSUAL EVENT EAL: EXPLOSION within the PROTECTED AREA Basis: This EAL addresses the magnitude and extent of FIRES or EXPLOSIONS that may be potentially significant precursors of damage to safety systems. It addresses the FIRE-EXPLOSION, and not the degradation in performance of affected systems that may result.As used here, detection is visual ebseR'atiOn and ropedt by plant personnel or sensor alr ThdieatiE)n.

EAL1#4 The 15 time period begins with a credible notfication that a FIRE i occur.ng o.indication of a fire detection system aarm.actu.ation.

Verification of a fire detection syte m alarm/actuation includes actions that can be taken within the control room or other nearby sitee specific loation to ensure that it is not spurious.

An alarm is assumed to be an indication of a FIRE it is disproved Within the 15 miRnut period by per-soG.n dispatched to the scene.In other words, a personnel ropGed fromF the scene may be used to disprove a sensor alarm it re~ei4'ved wJ`ithin 1 5 minutes of the alarm, but shall Rot be required to3 verify the alarm.The inteRt of this 15 Minute dur-ation is t size the FIRE aRd to disc-riminRate agaiRst sll or immediatel

.' adjacent WtoVTAL AREAS or oth÷r,ý sg"ificant bu#i,.ngs or areas. The intent o-ths !Q u isnto te ipkfin~d4s wareheo;;cis)r oF nea t~at aren ot 44 as"y Gontact with or ,mmediately' adjacent to WTAL AREAS. This ex.ludes FIRES within admin-istratio buildings, waste basket FIRES, and other small FIRES Of no sAft.' cOnsequence.

imp~eiat'y ad~ae~t.ýntfi.

es that the area imm~ediýate4,y adj cent contains orF m4ay contain Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HU2.2 SGS ECG -EAL Technical Bases EP-SC-111-208 equipm~ent or- cabling that could impact equipment located in VITAL AREA4S or the fire coul damage equipment inside VITA.L AREAS or- that pldes acceSS tO VITAL AREAS.]EAL7#2 This EAL addresses only those EXPLOSIONS of sufficient force to damage permanent structures or equipment within the PROTECTED AREA.No attempt is made to assess the actual magnitude of the damage. The occurrence of the EXPLOSION is sufficient for declaration.

The Emergency dreeter-Coordinator also needs to consider any security aspects of the EXPLOSION, if applicable.

Escalation of this emergency classification level, if appropriate, would be based on EAL HA2.2.Explanation/Discussion/Definitions:

If the EXPLOSION is determined to be hostile in nature, the event is classified under EAL HS4.1.Definitions:

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU2 Example EAL #2 Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HU2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-208 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: G-H_- Hazards & Other Conditions Affecting Plant Safety 2 -Fire or Explosion FIRE or EXPLOSION in a VITAL AREA affecting the operability of plant safety systems required to establish or maintain safe shutdown All HA2.1 -ALERT EAL: FIRE in ANY Table H-1 plant structure affecting the operability of plant safety systems required to establish or maintain safe shutdown AND_ 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Table H-1 Plant Structures Containing Safe Shutdown Systems or Components" Auxiliary Building" Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas* Containment" Fuel Handling Building" Service Building 0 RWST, PWST, and AFWST Area Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 Basis: VICLE- DAMAGE is Used to identify thc magnitude of the fire or explo.sion and t discrOimiate aaga-instimino fies ndexplosionS.

The reforen....

to struture cntaining safety systems or compon.ents is incue to discriimiate gans FIRES OF exlson naeas haVing a low probability of affecting safe_epei÷atiOR.

The significance here is not that a safety system was degraded but the fact that the FIRE er- EXPO-L-Q0N-was large enough to cause damage to these systems.The usf VjS{&L- gA fAE shoul no binepted as Mand~at!Rg a Iengthiy-4m assess men. p+rioto -lassificatiGR.

The declaration of an ALERT and the activation of the Technical Support Center will provide the Emergency DiFee-t4rCoordinator with the resources needed to perform detailed damage assessments.-The Emrgnc Dreotof-a4-Se-neeR---te G-'eensie anyG seuitly aset-fteE";I

[This EAL Should , site .pecific stuctur...

or- areas that cntain .. ,SYs component andl functions reqUlire d for Safc Shutdow~n Of the plant. Sit Slpecific Szafe S;hUt~down Escalation of this emergency classification level, if appropriate, will be based on EALs in Category S, System Malfunctions, Category F, Fission Product Barrier Degradation, or Category R, Abnormal Rad Levels / Rad ieogial Effluent4Gs.

Explanation/Discussion/Definitions:

The Table H-1 Plant Structures Containing Safe Shutdown Systems or Components include those plant structures identified as Seismic Category I.Definitions:

FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

VITAL AREAS: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA2 Example EAL #1 2. UFSAR 3.2 Classification of Structures, Components and Systems Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HA2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-208 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HA2.1 SGS ECG -EAL Technical Bases EP-SC-11 11-208 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: G-H_- Hazards & Other Conditions Affecting Plant Safety 2 -Fire or Explosion FIRE or EXPLOSION in a VITAL AREA affecting the operability of plant safety systems required to establish or maintain safe shutdown All HA2.2 -ALERT EAL: EXPLOSION in ANY Table H-1 plant structure affecting the operability of plant safety systems required to establish or maintain safe shutdown Table H-1 Plant Structures Containing Safe Shutdown Systems or Components" Auxiliary Building* Service Water Intake Structure* Control Point Area* Inner/Outer Penetration Areas* Containment

Fuel Handling Building* Service Building* RWST, PWST, and AFWST Area Basis: 1 -8SJLE-DAMA-E is used to identify the magnitude of the fire or explosion and to discriminate agcainst, m.inRe fires and explosions,.

The ref-erene to structures containing safety systems or omp..on...en.ts is included to discriminate against FIRES Or cx-P-IQSionS in arFeas- hav.ing a low probability of affec-ting sf operatie-The significance here is not that a s.af.ety system was degraded but.. thea......alen h caus damage t o ths syt e-tmthat the RR-rEXPLOSION was large enough to cause damage to these systems.Salem Page 1 of 3 Rev. 0 (draft E)EAL#: HA2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-208 The use of VISIBLE DAMAGE should not be intcrpreted as mandating a lengthy damnage assess ment prior to "laSSifi;ation.

The declaration of an ALERT and the activation of the Technical Support Center will provide the Emergency D-rector Coordinator with the resources needed to perform detailed damage assessments.

The Emergency Coordinator DireeteG-also needs to consider any security aspects of the EXPLOSION.

[This EAL shoeuld specify site spa cifiG structures or areas that contain safet SyStem7, a;cmnntandI fU 'n ctions, q-,I-, -- for- safe shutdown of the plant. Site &pee.'fiG Safe Shutdown na-lysi. a shoul-d be GGonsu1ted for- equipment and plant areas required to establish or m~aintain safe-shuftdowRA.

Escalation of this emergency classification level, if appropriate, will be based on EALs in Category S, System Malfunctions, Category F, Fission Product Barrier Degradation, or Category R, Abnormal Rad Levels / Rad ie4eGgial-Effluent4Gs.

Explanation/Discussion/Definitions:

If the EXPLOSION is determined to be hostile in nature, the event is classified under EAL HS4.1.The Table H-1 Plant Structures Containing Safe Shutdown Systems or Components include those plant structures identified as Seismic Category I.Definitions:

FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

VITAL AREAS: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: HA2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-208 OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA2 Example EAL #1 2. UFSAR 3.2 Classification of Structures, Components and Systems Salem Page 3 of 3 Rev. 0 (draft E)EAL#: HA2.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: G-H -Hazards & Other Conditions Affecting Plant Safety 3 -Hazardous Gas Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to NORMAL PLANT OPERATIONS All HU3.1 -UNUSUAL EVENT EAL: Release of toxic, corrosive, asphyxiant or flammable gas in amounts (excluding small or incidental releases) that have or could adversely affect NORMAL PLANT OPERATIONS Basis: This EAL is based on the release of toxic, corrosive, asphyxiant or flammable gases of sufficient quantity to affect normal plant operations.

The fact that SCBA or other respiratory protection may be worn does not eliminate the need to declare the event.This 1-0EAL is not intended to require significant assessment or quantification.

It assumes an uncontrolled process that has the potential to affect NORMAL PLANT OPERATIONS.

This would preclude small or incidental releases, or releases that do not impact structures needed for plant operation.

An asphyxiant is a gas capable of reducing the level of oxygen in the body to dangerous levels. Most commonly, asphyxiants work by merely displacing air in an enclosed environment.

This reduces the concentration of oxygen below the normal level of around 19%, which can lead to breathing difficulties, unconsciousness or even death.Escalation of this emergency classification level, if appropriate, would be based on EAL HA3.1.Explanation/Discussion/Definitions:

The release may have originated within the Site Boundary, or it may have originated offsite and subsequently drifted onto the Site Boundary.

Offsite events (e.g., tanker truck accident releasing toxic gases, etc.) resulting in the plant being within the evacuation area should also be considered in this EAL because of the adverse affect on NORMAL PLANT OPERATIONS.

Salem Page 1 of 4 Rev. 0 (draft E)EAL#: HU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-209 Should the release affect plant VITAL AREAS, escalation to an ALERT would be based on EAL HA3.1. Should an EXPLOSION or FIRE occur due to flammable gas within an affected plant area, an ALERT may be appropriate based on EAL HA2.1 or EAL HA2.2.A Toxic Gas is considered to be any substance that is dangerous to life or limb by reason of inhalation or skin contact.A Flammable Gas is considered to be any substance that can result in an ignition, sustained burn or detonation.

Carbon dioxide (C0 2) is an asphyxiant gas. A 20 lb CO 2 extinguisher discharge will not create a hazardous atmosphere unless the room volume is less than 2500 cubic feet.A Corrosive Gas is a highly reactive substance that causes obvious damage to living tissue.Corrosives act either directly, by chemically destroying the part or indirectly by causing inflammation.

Acids and bases are common corrosive materials.

Corrosives such as these are also sometimes referred to as caustics.This EAL should not be construed to include confined spaces that must be ventilated prior to entry or situations involving the fire department personnel who are using respiratory equipment during the performance of their duties unless it also affects personnel not involved with the fire department activates.

In addition, those situations that require personnel to wear respiratory protection equipment as the result of airborne contamination as required by Radiation Protection personnel do not meet the intent of this EAL.Definitions:

NORMAL PLANT OPERATIONS:

Activities at the plant site associated with routine testing, maintenance, or equipment operations, in accordance with normal operating or administrative procedures.

Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from NORMAL PLANT OPERATIONS.

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.Salem Page 2 of 4 Rev. 0 (draft E)EAL#: HU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-209 FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU3 Example EAL #1 2. OE25324 Alert Declared Due to C02 Fire Extinguisher Discharge Salem Page 3 of 4 Rev. 0 (draft E)EAL#: HU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-209 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: HU3.1 SGS ECG -EAL Technical Bases EP-SC-11 11-209 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C-H_- Hazards & Other Conditions Affecting Plant Safety 3 -Hazardous Gas Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to NORMAL PLANT OPERATIONS All HU3.2 -UNUSUAL EVENT (Common Site)Notification by Local, County, or State Officials for evacuation or sheltering of site personnel based on an off-site gas release event that includes toxic, corrosive, asphyxiant, or flammable gas Basis: Thiq -FAI -is, basd on th ose of tEoYio or5.v Gh~o o i m~~ ~o c., ~f ic~,r~+ ,',, ,~ r,+~+x, fr~ ',f4~r'f r~rrm'~ I ~I'-~r~+ ~r't,+~,-~

r~c.I t, ly-i ....-J, r-. ..... ., The fact that SCBA or other respiratory protection may be worn does not eliminate the need to declare the event.This IG is no~t intended to require significant -asses-sment or quantification.

it assumes an uncontrolled proces. t-a-as-t-hetet-iala opaeons. Thold prclude II " nr bJ i i r- i+.n i rIIinJiiaaný^o

-i c +k'o+ A,. c.+r, irfi ir o ' a e nr*. frr

in.n operation.

-- -, "'.V- F An asphyxiant is a gas capable of reducing the level of oxygen in the body to dangerous levels. Most commonly, asphyxiants work by merely displacing air in an enclosed environment.

This reduces the concentration of oxygen below the normal level of around 19%, which can lead to breathing difficulties, unconsciousness or even death.Escalation of this emergency classification level, if appropriate, would be based on EAL HA3.1.Explanation/Discussion/Definitions:

This EAL is based on the existence of an uncontrolled release originating offsite and local, county or state officials have reported the need for evacuation or sheltering of site personnel.

Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 State and local officials may determine the evacuation area for an offsite spill or release by using "The Emergency Response Guidebook (ERG2008)" developed by the US Department of Transportation.

Should the release affect plant VITAL AREAS, escalation to an ALERT would be based on EAL HA3.1. Should an EXPLOSION or FIRE occur due to flammable gas within an affected plant area, an ALERT may be appropriate based on EAL HA2.1.A Toxic Gas is considered to be any substance that is dangerous to life or limb by reason of inhalation or skin contact.A Flammable Gas is considered to be any substance that can result in an ignition, sustained burn or detonation.

Carbon dioxide (C02) is an asphyxiant gas. A 20 lb. C02 fire extinguisher discharge will not create a hazardous atmosphere unless the room volume is less than 2500 cu.ft.A Corrosive Gas is a highly reactive substance that causes obvious damage to living tissue.Corrosives act either directly, by chemically destroying the part or indirectly by causing inflammation.

Acids and bases are common corrosive materials.

Corrosives such as these are also sometimes referred to as caustics.Definitions:

NORMAL PLANT OPERATIONS:

Activities at the plant site associated with routine testing, maintenance, or equipment operations, in accordance with normal operating or administrative procedures.

Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from NORMAL PLANT OPERATIONS.

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU3 Example EAL #2 2. The Emergency Response Guide (ERG2008)3. OE25354 Alert Due to CO 2 Fire Extinguisher Discharge Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-209 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C-H_- Hazards & Other Conditions Affecting Plant Safety 3 -Hazardous Gas Access to a VITAL AREA is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of operable equipment required to maintain safe operations or safely shut down the reactor All EAL# & Classification Level: HA3.1 -ALERT EAL: Access to ANY Table H-1 plant structure is prohibited due to toxic, corrosive, asphyxiant, or flammable gases which jeopardize operation of systems required to maintain safe operations or safely shut down the reactor (Note 5)Note 5: If the equipment in the stated area was already inoperable, or out of service, before the event occurred, then this EAL should NOT be declared as it will have NO adverse impact on the ability of the plant to safely operate or safely shut down beyond that already allowed by Technical Specifications at the time of the event.Table H-1 Plant Structures Containing Safe Shutdown Systems or Components" Auxiliary Building* Service Water Intake Structure" Control Point Area* Inner/Outer Penetration Areas* Containment

Fuel Handling Building* Service Building" RWST, PWST, and AFWST Area Basis: Gases in a VITAL AREA can affect the ability to safely operate or safely shut down the reactor.Salem Page 1 of 4 Rev. 0 (draft E)EAL#: HA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-209 The fact that SCBA or other respiratory protection may be worn does not eliminate the need to declare the event.Declaration should not be delayed for confirmation from atmospheric testing if the atmosphere poses an immediate threat to life and health or an immediate threat of severe exposure to gases. This could be based upon documented analysis, indication of personal ill effects from exposure, or operating experience with the hazards.f-theu i the stated area was already inoperable, or out of se..ice, before the ev occrrd, hc tI-; E7AL shul )oe dec~lared as it will have no) adverse im~pact On the ability of the-p'n-o-afl o ertor safely shutdeWn beyond that already allowed by Technical Mpecficat~ions at thQieoZteeet An asphyxiant is a gas capable of reducing the level of oxygen in the body to dangerous levels. Most commonly, asphyxiants work by merely displacing air in an enclosed environment.

This reduces the concentration of oxygen below the normal level of around 19%, which can lead to breathing difficulties, unconsciousness or even death.An uncontrolled release of flammable gasses within a facility structure has the potential to affect safe operation of the plant by limiting either operator or equipment operations due to the potential for ignition and resulting equipment damage/personnel injury. Flammable gasses, such as hydrogen and acetylene, are routinely used to maintain plant systems (hydrogen) or to repair equipment/components (acetylene

-used in welding).

This EAL assumes concentrations of flammable gasses which can ignite/support combustion.

Escalation of this emergency classification level, if appropriate, will be based on EALs in Category S, System Malfunctions, Category F, Fission Product Barrier Degradation, or Category R, Abnormal Rad Levels / Radioactive Effluent ,Cs.Explanation/Discussion/Definitions:

This EAL is based on gases that have entered a plant structure in concentrations that could be unsafe for plant personnel and, therefore, preclude access to equipment necessary for the safe operation or safe shutdown of the plant. The Table H-1 Plant Structures Containing Safe Shutdown Systems or Components include those plant structures identified as Seismic Category I.A Toxic Gas is considered to be any substance that is dangerous to life or limb by reason of inhalation or skin contact.A Flammable Gas is considered to be any substance that can result in an ignition, sustained burn or detonation.

Carbon dioxide (CO 2) is an asphyxiant gas. A 20 Ib CO 2 extinguisher discharge will not create a hazardous atmosphere unless the room volume is less than 2500 cubic feet.Salem Page 2 of 4 Rev. 0 (draft E)EAL#: HA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-209 A Corrosive Gas is a highly reactive substance that causes obvious damage to living tissue.Corrosives act either directly, by chemically destroying the part or indirectly by causing inflammation.

Acids and bases are common corrosive materials.

Corrosives such as these are also sometimes referred to as caustics.This EAL should not be construed to include confined spaces that must be ventilated prior to entry or situations involving the fire department personnel who are using respiratory equipment during the performance of their duties unless it also affects personnel not involved with the fire department activates.

In addition, those situations that require personnel to wear respiratory protection equipment as the result of airborne contamination as required by Radiation Protection personnel do not meet the intent of this EAL.Definitions:

VITAL AREA: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROTECTED AREA (PA): A security controlled area within the OWNER CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA3 Example EAL #1 2. UFSAR 3.2 Classification of Structures, Components and Systems 3. OE25324 Alert Declared Due to C02 Fire Extinguisher Discharge Salem Page 3 of 4 Rev. 0 (draft E)EAL#: HA3.1 SGS ECG -EAL Technical Bases EP-SC-111-209 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: HA3.1

SGS ECG -EAL Technical Bases EP-SC-1 11-210 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

H -Hazards & Other Conditions Affecting Plant Safety 4 -Security Confirmed SECURITY CONDITION or threat which indicates a potential degradation in the level of safety of the plant All EAL# & Classification Level: HU4.1 -UNUSUAL EVENT (Common Site)EAL: A SECURITY CONDITION that does NOT involve a HOSTILE ACTION as reported by the Security Operations Supervisor or designee (Note 8)OR Receipt of a CREDIBLE/ACTUAL THREAT to Salem or Hope Creek station -(determined by security in accordance with SY-AA-1 01-132, "Threat Assessment") (Note 8)OR A VALIDATED notification from NRC providing information of a Salem/Hope Creek AIRCRAFT threat (Note 8)NOTE 8: Shift Manager (SM) should implement the Prompt Actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification of a security emergency.

Key Information to obtain from Security Supervision upon SM notification of a security event:* Determination if the security event is a HOSTILE ACTION or SECURITY CONDITION* If a HOSTILE ACTION, is location the OCA or PA?Basis: Security events which do not represent a potential degradation in the level of safety of the plant are reported under 10 CFR 73.71 or in some cases under 10 CFR 50.72. Security events assessed as HOSTILE ACTIONS are classifiable under EAL HA4.1, EAL HS4.1 and EAL HG4.1.Salem Page 1 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 A higher initial classification could be made based upon the nature and timing of the security threat and potential consequences.

The liGesee-Emergency Coordinator-shall consider upgrading the emergency response status and emergency classification level in accordance with the Salem -Hope Creek Security Contingency Plans-te's Safeguards Plan and 'Emergency Plan.EAL#1 st Condition (SECURITY CONDITION)

Reference is made to site-the specific security shift supervision (Security Operations Supervisor or designee) because these individuals are the designated personnel on-site qualified and trained to confirm that a security event is occurring or has occurred.

Training on security event classification confirmation is closely controlled due to the strict secrecy controls placed on the Salem -Hope Creek Security Contingency PlanplaRt Safeguards Cont.i..,n,..n Plaei.This threshold is based on site specifi. Gsecuity plans-the Salem -Hope Creek Security Contingency Plan. Site SPecific Safeguards CoRtingency Plans aeThe Salem -Hope Creek Security Contingency Plan is based on guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Security Contingency Plan and ISFSI Program.EAL-#22nd Condition (CREDIBLE

/ ACTUAL THREAT)This threshold is included to ensure that appropriate notifications for the security threat are made in a timely manner. This includes information of a credible threat. Only the site to which the specific threat is made needs declare the Notification of an UNUSUAL EVENT.The determination of CREDIBLE is made through use of information found in Threat Assessment, SY-AA-101-132t site o ef Safeguards

....... DRG E, 4 L-#3 3 rd Condition (AIRCRAFT Threat)The intent of this part of the EAL is to ensure that notifications for the AIRCRAFT threat are made in a timely manner and that offsite response organization (OROs) and plant personnel are at a state of heightened awareness regarding the credible threat. It is not the intent of this EAL to replace existing non-hostile related EALs involving AIRCRAFT.This EAL is met when a plant (site) receives information regarding an AIRCRAFT threat from NRC. Validation is performed by calling the NRC or by other approved methods of authentication.

Only the site to which the specific threat is made need declare the UNUSUAL EVENT.Salem Page 2 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -210 The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an AIRLINER (AIRLINER is meant to be a large AIRCRAFT with the potential for causing significant damage to the plant). The status and size of the plane may be provided by NORAD through the NRC.Escalation to ALERT emergency classification level would be via EAL HA4.1 and would be appropriate if the threat involves an AIRLINER within 30 minutes of the plant or a HOSTILE ACTION in the OCA or PA.Explanation/Discussion/Definitions:

If the security events do not meet the threshold for an UNUSUAL EVENT classification, they may result in the need to make a non-emergency report per RAL Section 11.7.1 .a, One Hour Non-Emergency Safeguards Event (10 CFR 73.71) as determined by Security per SY-AA-1002, "Safeguards Event Report." Security will be focused on actions to mitigate the security event and will provide the SM with key information as the event progresses.

Communications between the SMs and the Security Team Leader should be accurate, concise, and focused on EAL criteria and protection of key target sets. As Security and Operations terminology sometimes differ, clarifying questions should be asked to ensure accurate information exchange.1 st Condition (SECURITY CONDITION)

Page 6 of this EAL Basis is a "Security Contingency Event Summary Table" that indicates which Security Contingency Events could result in Security Supervision determining that a SECURITY CONDITION exists and therefore an UNUSUAL EVENT classification should be made OR, could result in Security Supervision determining that a HOSTILE ACTION is or has occurred and therefore classification at the ALERT or higher level should be made based on the location (OCA or PA) of the HOSTILE ACTION.2 nd Condition (CREDIBLE

/ ACTUAL THREAT)This threshold is included to ensure that threat information from any source which is assessed by security supervision as being a "CREDIBLE/ACTUAL THREAT" is classified as an UNUSUAL EVENT. Only the site to which the specific threat is made needs to declare the UNUSUAL EVENT. For Security Events, Salem and Hope Creek is considered a single site, therefore a "CREDIBLE/ACTUAL THREAT" to either Salem or Hope Creek would affect the entire site and a "Common Site" UE declaration would be made.Timely classification will ensure that Offsite Response Organizations and plant personnel are notified in a timely manner resulting in a state of heightened awareness.

Threats are evaluated by security per Threat Assessment, SY-AA-101-132.

Security threats that do not meet the definition of a "CREDIBLE/ACTUAL THREAT" should be dispositioned lAW Threat Assessment, SY-AA-101-132.

Salem Page 3 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 3 rd Condition (AIRCRAFT Threat)AIRCRAFT threat calls from the NRC should be VALIDATED by use of NRC authentication code or a return call to the NRC Headquarter Operations Center.For security events, Salem and Hope Creek is considered a single site, therefore, a"VALIDATED AIRCRAFT THREAT" to either Salem or Hope Creek would affect the entire site and a "Common Site" UE declaration would be made.Definitions:

SECURITY CONDITION:

Any security event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.VALIDATED:

AIRCRAFT threat call from the NRC that is confirmed to be authentic.

Calls from the NRC are VALIDATED by use of the NRC provided authentication code or by making a return call to the NRC Headquarter Operations Center and confirming threat information with the NRC Operation Officer. AIRCRAFT threat calls from other agencies, NORAD, FAA, or FBI should be VALIDATED by calling the NRC Operations Officer.AIRCRAFT:

Includes both small and large AIRCRAFT.

Examples of AIRCRAFT include general aviation Cessna, Piper and Lear type private planes, large passenger or freight planes as well as police, medical and media helicopters.

A large AIRCRAFT is referred to as an AIRLINER.AIRLINER/LARGE AIRCRAFT:

Any size or type of AIRCRAFT with the potential for causing significant damage to the plant (refer to the Security Contingency Plan for a more detailed definition).

CREDIBLE I ACTUAL THREAT: Is a threat which poses a likely and serious danger to the safe operation of the facility or to site personnel and public safety.HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OCA).Salem Page 4 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, the area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security center.PROJECTILE:

An object that impacts Salem/Hope Creek that could cause concern for continued operability, reliability, or personnel safety.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU4 Example EAL #1, #2, #3 2. Salem -Hope Creek Security Contingency Plan 3. SY-AA-101-132 Threat Assessment

4. SC.OP-AB.CR-0004(Q)

-Security Event 5. SC.OP-AB.CR-0005(Q)

-Airborne Threat Salem Page 5 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Security Contingency Event Summary Table Event Could Event Could Result in Result in Contingency Contingency Determination Determination Event of a of a Number Event SECURITY HOSTILE Title CONDITION ACTION (UE ONLY) (ALERT or Higher)Yes / No Yes / No# 1 Malevolent Threat / Use of a Vehicle Yes Yes# 2 Detection of Impending Attack / Threat Directed Yes Yes Armed Attack# 3 Civil Disturbance Yes No# 4 PA/VA Intrusion or Detection of a Breached Barrier No Yes# 5 Fire / Explosion or other Catastrophic Event Yes Yes# 6 Detection of Aberrant Behavior No No# 7 Security Force Strike / Unavailability of Security No No Force# 8 Loss of Contact with Security Officer Yes Yes# 9 Confirmed Sabotage / Tampering

/ Vandalism

/ Yes Yes Malicious Mischief# 10 Bomb Threat / Explosive Device Discovered Yes Yes# 11 Loss of Onsite / Offsite Security Communications Yes No# 12 Loss of Security System Power Yes No# 13 Loss of Alarm Assessment Capability Yes No# 14 Loss of Security Lighting Yes No# 15 Loss of Security Computer Yes No# 16 Extortion

/ Coercion / Hostage Threat Yes Yes# 17 Waterborne Threat Yes Yes# 18 Coordinated Land Vehicle Bomb Attack No Yes# 19 Standoff Attack by a Sniper Yes Yes# 20 Insider Threat Yes No Salem Page 6 of 6 Rev. 0 (draft E)EAL#: HU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: H -Hazards & Other Conditions Affecting Plant Safety 4 -Security HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat All HA4.1 -ALERT A HOSTILE ACTION is occurring or has occurred within the OCA as reported by the Security Operations Supervisor or designee (Note 8)OR A VALIDATED notification from NRC of a AIRLINER attack threat < 30 minutes away from Salem/Hope Creek (Note 8)NOTE 8: Shift Manager (SM) should implement the Prompt Actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification of a security emergency.

Key Information to obtain from Security Supervision upon SM notification of a security event: " Determination if the security event is a HOSTILE ACTION or SECURITY CONDITION* If a HOSTILE ACTION, is location the OCA or PA?Basis: These-This EALs addresses the contingency for a very rapid progression of events, such as that experienced on September 11, 2001. They are not premised solely on the potential for a radiological release. Rather the issue includes the need for rapid assistance due to the possibility for significant and indeterminate damage from additional air, land or water attack elements.The fact that the site is under serious attack or is an identified attack target with minimal time available for further preparation or additional assistance to arrive requires a heightened state of readiness and implementation of protective measures that can be effective (such as on-site evacuation, dispersal or sheltering).

Salem Page 1 of 6 Rev. 0 (draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -210 E, 4 t#!4 1 st Condition (OCA HOSTILE ACTION)This EAL addresses the potential for a very rapid progression of events due to a HOSTILE ACTION within or directed towards the OWNER CONTROLLED AREA (OCA). It is not intended to address incidents that are accidental events or acts of civil disobedience, such as small AIRCRAFT impact, hunters, or physical disputes between employees within the OWNER CONTROLLED AREAOCAGGA.

Those events are adequately addressed by other EALs or RALs Note that this EAL is applicable for any HOSTILE ACTION occurring, or that has occurred, in the OWNER CONTROLLED AREA. This ic'luds the lSFSI, ,ocated within Salem,-/Hope Creek PROTECTED AREA.If not previously notified by the NRC that the airborne HOSTILE ACTION was intentional, then it would be expected, although not certain, that notification by an appropriate Federal agency would follow. In this case, appropriate federal agency is intended to be NORAD, FBI, FAA or NRC. However, the declaration should not be unduly delayed awaiting Federal notification.

EAL,#22nd Condition (AIRLINER Threat)This EAL addresses the immediacy of an expected threat (AIRLINER) arrival or impact on the site within a relatively short time (< 30 minutes).The intent of this EAL is to ensure that notifications for the AIRLINER attack threat are made in a timely manner and that OROs and plant personnel are at a state of heightened awareness regarding the credible threat. AIRLINER is meant to be a large AIRCRAFT with the potential for causing significant damage to the pI4i#site.

This EAL is met when a plant receives information regarding an AIRLINER attack threat from NRC and the AIRLINER is within 30 minutes of the plant. Only the site to which the specific threat is made need declare the ALERT.The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an AIRLINER (AIRLINER is meant to be a large AIRCRAFT with the potential for causing significant damage to the plant). The status and size of the plane may be provided by NORAD through the NRC.Salem Page 2 of 6 Rev. 0 (draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Explanation/Discussion/Definitions:

This event will be escalated to a SITE AREA EMERGENCY based upon HOSTILE ACTION affecting the PROTECTED AREA (PA). Also, if Hope Creek declares an SAE due to their PA being affected by the security event, Salem will escalate to SAE to match them.1 st Condition (OCA HOSTILE ACTION)Reference is made to the specific security shift supervision (Security Operations Supervisor or designee) because these individuals are the designated personnel on-site qualified and trained to confirm that a HOSTILE ACTION is occurring or has occurred.This EAL condition is not premised solely on adverse health effects caused by a radiological release. Rather the issue is the immediate need for assistance due to the nature of the event and the potential for significant and indeterminate damage. Although nuclear plant security officers are well trained and prepared to protect against HOSTILE ACTION, it is appropriate for Offsite Response Organizations (OROs) to be notified and encouraged to begin activation to be better prepared should it be necessary to consider further actions.Page 6 of this EAL Basis is a "Security Contingency Event Summary Table" that indicates which Security Contingency Events could result in Security Supervision determining that a HOSTILE ACTION is or has occurred and therefore classification at the ALERT or higher level should be made based on the location (OCA or PA) of the HOSTILE ACTION. Security events that do not involve a HOSTILE ACTION may result in Security Supervision determining that a SECURITY CONDITION exists and therefore an UNUSUAL EVENT classification should be made per EAL HU4.1.2 nd Condition (AIRLINER Threat)The fact that the site is an identified attack candidate with minimal time available for further preparation requires a heightened state of readiness and implementation of protective measures that can be effective (onsite evacuation, dispersal, or sheltering) before arrival or impact.This EAL is met when a plant receives VALIDATED information regarding an AIRLINER attack threat from NRC and the AIRLINER is less than 30 minutes away from the site. Only the site (Salem and Hope Creek is considered a single site for Security event classifications) to which the specific threat is made needs declare the ALERT.AIRLINER threat calls from the NRC should be VALIDATED by use of NRC authentication code or a return call to the NRC Headquarter Operations Center.Salem Page 3 of 6 Rev. 0 (draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OWNER CONTROLLED AREA).OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.AIRCRAFT:

Includes both small and large AIRCRAFT.

Examples of AIRCRAFT include general aviation Cessna, Piper and Lear type private planes, large passenger or freight planes as well as police, medical and media helicopters.

A large AIRCRAFT is referred to as an AIRLINER.AIRLINER/LARGE AIRCRAFT:

Any size or type of AIRCRAFT with the potential for causing significant damage to the plant (refer to the Security Contingency Plan for a more detailed definition).

SECURITY CONDITION:

Any security event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.PROJECTILE:

An object directed toward Salem/Hope Creek that could cause concern for its continued operability, reliability, or personnel safety.I , Salem Page 4of 6 Rev. 0(draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 VALIDATED:

AIRCRAFT threat call from the NRC that is confirmed to be authentic.

Calls from the NRC are VALIDATED by use of the NRC provided authentication code or by making a return call to the NRC Headquarter Operations Center and confirming threat information with the NRC Operation Officer. AIRCRAFT threat calls from other agencies, NORAD, FAA, or FBI should be VALIDATED by calling the NRC Operations Officer.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA4 Example EAL #1, #2 2. Salem -Hope Creek Security Contingency Plan 3. SC.OP-AB.CR-0004(Q)

-Security Event 4. SC.OP-AB.CR-0005(Q)

-Airborne Threat Salem Page 5 of 6 Rev. 0 (draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Security Contingency Event Summary Table Event Could Event Could Result in Result in Contingency Contingency Determination Determination Event of a of a Number Event SECURITY HOSTILE Title CONDITION ACTION (UE ONLY) (ALERT or Higher)Yes / No Yes / No# 1 Malevolent Threat / Use of a Vehicle Yes Yes# 2 Detection of Impending Attack / Threat Directed Yes Yes Armed Attack# 3 Civil Disturbance Yes No# 4 PA/VA Intrusion or Detection of a Breached Barrier No Yes# 5 Fire / Explosion or other Catastrophic Event Yes Yes# 6 Detection of Aberrant Behavior No No# 7 Security Force Strike / Unavailability of Security No No Force# 8 Loss of Contact with Security Officer Yes Yes# 9 Confirmed Sabotage / Tampering

/ Vandalism

/ Yes Yes Malicious Mischief# 10 Bomb Threat / Explosive Device Discovered Yes Yes# 11 Loss of Onsite / Offsite Security Communications Yes No# 12 Loss of Security System Power Yes No# 13 Loss of Alarm Assessment Capability Yes No# 14 Loss of Security Lighting Yes No# 15 Loss of Security Computer Yes No# 16 Extortion

/ Coercion / Hostage Threat Yes Yes# 17 Waterborne Threat Yes Yes# 18 Coordinated Land Vehicle Bomb Attack No Yes# 19 Standoff Attack by a Sniper Yes Yes# 20 Insider Threat Yes No Salem Page 6 of 6 Rev. 0 (draft E)EAL#: HA4.1 SGS ECG -EAL Technical Bases EP-SC-11 11 -210 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: H -Hazards & Other Conditions Affecting Plant Safety 4 -Security HOSTILE ACTION within the PROTECTED AREA All HS4.1 -SITE AREA EMERGENCY A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the Security Operations Supervisor or designee (Note 8)NOTE 8: Shift Manager (SM) should implement the Prompt Actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification of a security emergency.

Key Information to obtain from Security Supervision upon SM notification of a security event: Determination if the security event is a HOSTILE ACTION or SECURITY CONDITION* If a HOSTILE ACTION, is location the OCA or PA?Basis: This condition represents an escalated threat to plant safety above that contained in the ALERT in that a HOSTILE FORCE has progressed from the OWNER CONTROLLED AREA to the PROTECTED AREA.This EAL addresses the contingency for a very rapid progression of events due to a HOSTILE ACTION within or directed towards the PROTECTED AREA (PA). Plant VITAL AREAS are within the PROTECTED AREA and are aenerallv controlled by card key readers. A HOSTILE ACTION in the PROTECTED AREA (which includes VITAL AREAS) could represent a situation that threatens the safety of plant personnel and the general public.Salem Page 1 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 These EALs address the contingency for a very rapid progression of events, -such as that experienced on September 11, 2001. It is not premised solely on the potential for a radiological release. Rather the issue includes the need for rapid assistance due to the possibility for significant and indeterminate damage from additional air, land or water attack elements.The fact that the site is under serious attack with minimal time available for further preparation or additional assistance to arrive requires Offsite Response Organization (ORO) readiness and preparation for the implementation of protective measures.This EAL addresses the potential for a ve..' rapid prog.reSSion of events due to a HOST!LE AGT-IN. it.-is not intended to address incidents that are accidental events or acts of civil disobedience, such as small AIRCRAFT impact, hunters, or physical disputes between employees within the PROTECTED AREA. Those events are adequately addressed by other EALs or RALs.fAlthough nuclear plant security officers are well trained and prepared to protect against HOSTILE ACTION, it is appropriate for OROs to be notified and encouraged to begin preparations for public protective actions (if they do not to be better prepared should it be necessary to consider further actions.]fIf not previously notified by NRC that the airborne HOSTILE ACTION was intentional, then it would be expected, although not certain, that notification by an appropriate Federal agency would follow. In this case, appropriate federal agency is intended to be NORAD, FBI, FAA or NRC. However, the declaration should not be unduly delayed awaiting Federal notification.]

Escalation of this emergency classification level to a GENERAL EMERGENCY, if appropriate, would be based upon the actual loss of physical control of the facility.

If necessary, Salem will declare this event.on actual plant status after im-pact or progression of attack.Explanation/Discussion/Definitions:

The Security Shift Supervision is defined as the Security Operations Supervisor or designee.These individuals are the designated on-site personnel qualified and trained to confirm that a security event is occurring or has occurred.

Training on security event classification confirmation is closely controlled due to the strict secrecy controls placed on the Salem -Hope Creek Security Contingency Plan (Safeguards) information.

PROJECTILES that are directed into or that have impacted the PA from the OCA or beyond are considered under this EAL as HOSTILE ACTIONS within the PA.Salem Page 2 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Page 5 of this EAL Basis is a "Security Contingency Event Summary Table" that indicates which Security Contingency Events could result in Security Supervision determining that a HOSTILE ACTION is or has occurred and therefore classification at the ALERT or higher level should be made based on the location (OCA or PA) of the HOSTILE ACTION. Security events that do not involve a HOSTILE ACTION may result in Security Supervision determining that a SECURITY CONDITION exists and therefore an UNUSUAL EVENT classification should be made per EAL HU4.1.Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OCA).OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.HOSTILE FORCE: One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.

HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.SECURITY CONDITION:

Any security event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.AIRCRAFT:

Includes both small and large AIRCRAFT.

Examples of AIRCRAFT include general aviation Cessna, Piper and Lear type private planes, large passenger or freight planes as well as police, medical and media helicopters.

A large AIRCRAFT is referred to as an AIRLINER.Salem Page 3 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 AIRLINER/LARGE AIRCRAFT:

Any size or type of AIRCRAFT with the potential for causing significant damage to the plant (refer to the Security Contingency Plan for a more detailed definition).

PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability, or personnel safety.VITAL AREAS: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA4 Example EAL #1, #2 2. Salem -Hope Creek Security Contingency Plan 3. SC.OP-AB.CR-0004(Q)

-Security Event 4. SC.OP-AB.CR-0005(Q)

-Airborne Threat Salem Page 4 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 Security Contingency Event Summary Table Event Could Event Could Result in Result in Contingency Contingency Determination Determination Event of a of a Number Event SECURITY HOSTILE Title CONDITION ACTION (UE ONLY) (ALERT or Higher)Yes / No Yes / No# 1 Malevolent Threat / Use of a Vehicle Yes Yes# 2 Detection of Impending Attack / Threat Yes Yes Directed Armed Attack# 3 Civil Disturbance Yes No# 4 PA/VA Intrusion or Detection of a Breached No Yes Barrier# 5 Fire / Explosion or other Catastrophic Event Yes Yes# 6 Detection of Aberrant Behavior No No# 7 Security Force Strike / Unavailability of No No Security Force# 8 Loss of Contact with Security Officer Yes Yes# 9 Confirmed Sabotage / Tampering

/ Vandalism

/ Yes Yes Malicious Mischief# 10 Bomb Threat / Explosive Device Discovered Yes Yes# 11 Loss of Onsite / Offsite Security Yes No Communications

12 Loss of Security System Power Yes No# 13 Loss of Alarm Assessment Capability Yes No# 14 Loss of Security Lighting Yes No# 15 Loss of Security Computer Yes No# 16 Extortion

/ Coercion / Hostage Threat Yes Yes# 17 Waterborne Threat Yes Yes#18 Coordinated Land Vehicle Bomb Attack No Yes# 19 Standoff Attack by a Sniper Yes Yes# 20 Insider Threat Yes No Salem Page 5 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 This page intentionally blank I i Salem Page 6 of 6 Rev. 0 (draft E)EAL#: HS4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: H -Hazards & Other Conditions Affecting Plant Safety 4 -Security HOSTILE ACTION resulting in loss of physical control of the facility All HG4.1 -GENERAL EMERGENCY A HOSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions (i.e., reactivity control, RCS inventory, or secondary heat removal) at Salem or Hope Creek (Note 8)OR A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely at Salem or Hope Creek (Note 8)NOTE 8: Shift Manager (SM) should implement the Prompt Actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification of a security emergency.

Key Information to obtain from Security Supervision upon SM notification of a security event: " Determination if the security event is a HOSTILE ACTION or SECURITY CONDITION* If a HOSTILE ACTION, is location the OCA or PA?Basis: EAL-#-1st Condition This EAL encompasses conditions under which a HOSTILE ACTION has resulted in a loss of physical control of VITAL AREAS (containing vital equipment or controls of vital equipment) required to maintain safety functions and control of that equipment cannot be transferred to and operated from another location.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: HG4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 fTypically, these safety functions are reactivity control (ability to shut down the reactor and keep it shutdown), reactor Water levcRCS inventoryo (ability to cool the core), and dGGa heatsecondary heat removal (ability to maintain a heat Sinkremove decay heat): fr -aBWR The equivalcnt functions for a PWR are reactivity control, ReS inventery, and seonfdarr heat Femevab1[Loss of phySiGal contro-I f the room o remoete shutdown capability alone mnay not prevent the ability to mnaintain safety functions per Se. Design of the remote shutdown capablthy and the location of the trans for S~itchels shoul-1d be taken into account. Primnary emphasis should be placed on those components and instru~ments that supply protection for and information about safety functions.]

If control of the plant equipment necessary to maintain safety functions can be transferred to another location, then the threshold is not met.EAL-#22nd Condition This EAL addresses failure of spent fuel cooling systems as a result of HOSTILE ACTION if IMMINENT fuel damage is likely, such as when a freshly off loaded reactor core is in the spent fUel-P991.

[A freshly off loaded reactor coef is defined by site specific criteria.]

Explanation/Discussion/Definitions:

Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OCA).PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability, or personnel safety.VITAL AREAS: Typically any site specific areas, normally within the PROTECTED AREA, that contains equipment, systems, components, or material, the failure, Salem Page 2 of 5 Rev. 0 (draft E)EAL#: HG4.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -210 destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .Salem Page 3 of 5 Rev. 0 (draft E)EAL#: HG4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HG1 Example EAL #1, #2 2. SC.OP-AB.CR-0004(Q)

-Security Event 3. SC.OP-AB.CR-0005(Q)

-Airborne Threat Salem Page 4 of 5 Rev. 0 (draft E)EAL#: HG4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-210 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: HG4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-211 EAL Category:

G-H__- Hazards & Other Conditions Affecting Plant Safety EAL Subcategory:

5 -Control Room Evacuation Initiating Condition:

Control Room evacuation has been initiated Mode Applicability:

All EAL# & Classification Level: HA5.1 -ALERT EAL: Control Room evacuation has been initiated Basis: With the Ceontrol Rfoom evacuated, additional support, monitoring and direction through the Technical Support Center and/or other emergency response facilities may be necessary.

Inability to establish plant control from outside the _Control R-room will escalate this event to a SITE AREA EMERGENCY per EAL HS5.1.Explanation/Discussion/Defi nitions: Control Room evacuation represents a serious plant situation since the degree of plant control at the Remote Shutdown Panel (RSP) is not as complete as from the Control Room. The intent of this EAL is to declare an ALERT when the determination to evacuate the Control Room has been made based on environmental/personnel safety concerns, and the physical process of evacuating the Control Room per S1(S2).OP-AB.CR-0001(Q), Control Room Evacuation, or S1 (S2).OP-AB.CR-0002(Q)

Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room or 4kV Switchgear Room, has commenced.

The Shift Manager (SM) determines if the Control Room requires evacuation.

Control Room inhabitability may be caused by fire, dense smoke, noxious fumes, bomb threat in or adjacent to the Control Room, or other life threatening conditions.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA5 Example EAL #1 2. SI(S2).OP-AB.CR-0001(Q)

Control Room Evacuation

3. S1(S2).OP-AB.CR-0002(Q)

Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room or 4kV Switchgear Room 4. SC.OP-AB.CR-0003(Q)

Control Room Habitability Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HA5.1 SGS ECG -EAL Technical Bases EP-SC-11 11-211 This Daae intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-211 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C-H_- Hazards & Other Conditions Affecting Plant Safety 5 -Control Room Evacuation Control Room evacuation has been initiated and plant control CANNOT be established All EAL# & Classification Level: HS5.1 -SITE AREA EMERGENCY EAL: Control Room evacuation has been initiated AND Control of the plant CANNOT be established within 15 minutes (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: The intent of this IG-EAL is to capture those events where control of the plant cannot be reestablished in a timely manner. In this case, expeditious transfer of control of safety systems has not occurred (although fission product barrier damage may not yet be indicated).

The intent of the EAL is to establish control of important plant equipment and knowledge of important plant parameters in a timely manner. Primary emphasis should be placed on those components and instruments that supply protection for and information about safety functions.

Typ'Ga4ly-tThese safety functions are reactivity control (ability to shutdown the reactor and maintain it shutdown), reactor water levelRCS inventory control (ability to cool the core), and decay-secondary heat removal (ability to maintain a heat sink). a BWR. The equivalet func~tions for a PWVR are reactivity conrol1, RCS invI.entor', and Secondary heat removal.The determination of whether or not control is established at the remote shutdown panel is based on Emergency DireoteFr-Coordinator (ED}-judgment.

The Emergency Direetor-Coordinator is expected to make a reasonable, informed judgment within the site time fe-rtr-apsfeiallocated 15 minutes that the licensee has control of the plant from the remote shutdown panel.[The-t si p ii tm o rnfer :s based on aayIs TOTsamnt st e g.c~nnnfnl nI14. -Q A-lffi t i rnn Lnnnm- nr ir nn n inmn n Thic irnn cJbri" 4-Pot Po, PP1 15 wnnt~wtot diin~ utfiofn r 140.a -Salem Page 1 of 4 Rev. 0 (draft E)EAL#: HS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-211 Escalation of this emergency classification level, if appropriate, would be by EALs in Category F, Fission Product Barrier Degradation, or Category R, Abnormal Rad Levels/Radioeoegial Effluent-EALs.

Salem Page 2 of 4 Rev. 0 (draft E)EAL#: HS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-211 Explanation/Discussion/Definitions:

The Shift Manager determines if the Control Room is inoperable and requires evacuation.

Control Room inhabitability may be caused by fire, dense smoke, noxious fumes, bomb threat in or adjacent to the Control Room, or other life threatening conditions.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HS5 Example EAL #1 2. SI(S2).OP-AB.CR-0001(Q)

Control Room Evacuation

3. Sl(S2).OP-AB.CR-0002(Q)

Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room or 4kV Switchgear Room 4. SC.OP-AB.CR-0003(Q)

Control Room Habitability Salem Page 3 of 4 Rev. 0 (draft E)EAL#: HS5.1 SGS ECG -EAL Technical Bases This page intentionally blank EP-SC-1 11-211 Salem Page 4 of 4 Rev. 0 (draft E)EAL#: HS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-212 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H_- Hazards & Other Conditions Affecting Plant Safety 6 -EC Judgment Other conditions exist which in the judgment of the Emergency Coordinator warrant declaration of an UNUSUAL EVENT All EAL# & Classification Level: HU6.1 -UNUSUAL EVENT EAL: Other conditions exist which in the judgment of the Emergency Coordinator indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

NO releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs Basis: This EAL addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency D4-eete-Coordinator to fall under the UNUSUAL EVENT NOUE emergency classification level.Explanation/Discussion/Definitions:

None EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HU5 Example EAL #1 Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-212 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -212 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: G-H_- Hazards & Other Conditions Affecting Plant Safety 6 -EC Judgment Other conditions exist which in the judgment of the Emergency Coordinator warrant declaration of an ALERT All HA6.1 -ALERT Other conditions exist which in the judgment of the Emergency Coordinator indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. ANY releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels Basis: This EAL addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency DirectGr Coordinator to fall under the ALERT emergency classification level.Explanation/Discussion/Definitions:

Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek plants.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for its continued operability, reliability, or personnel safety.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HA6.1 SGS ECG -EAL Technical Bases EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HA6 Example EAL #1 EP-SC-1 11-212 Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HA6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-212 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

G-H_- Hazards & Other Conditions Affecting Plant Safety 6 -EC Judgment Other conditions exist which in the judgment of the Emergency Coordinator warrant declaration of a SITE AREA EMERGENCY All EAL# & Classification Level: HS6.1 -SITE AREA EMERGENCY EAL: Other conditions exist which in the judgment of the Emergency Coordinator indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. ANY releases are NOT expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary Basis: This EAL addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency D4reetOr-Coordinator to fall under the emergency classification level description for SITE AREA EMERGENCY.

Explanation/Discussion/Definitions:

Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek plants.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HS6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-212 PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for its continued operability, reliability, or personnel safety.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HS3 Example EAL #1 I I Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HS6.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -212 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C-H_- Hazards & Other Conditions Affecting Plant Safety 6 -EC Judgment Other conditions exist which in the judgment of the Emergency Coordinator warrant declaration of a GENERAL EMERGENCY All HG6.1 -GENERAL EMERGENCY Other conditions exist which in the judgment of the Emergency Coordinator indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area Basis: This EAL addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director Coordinator to fall under the emergency classification level description for GENERAL EMERGENCY.

Explanation/Discussion/Definitions:

Definitions:

HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force.Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek plants.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for its continued operability, reliability, or personnel safety.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: HG6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-212 IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, HG2 Example EAL #1 Salem Page 2 of 2 Rev. 0 (draft E)EAL#: HG6.1 EALs for: Systems Malfunctions

SGS ECG -EAL Technical Bases EP-SC-1 11 -213 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 1 -Loss of AC Power Loss of all offsite AC power to vital buses for 15 minutes or longer 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown EAL# & Classification Level: SUI.1 -UNUSUAL EVENT EAL: Loss of all Offsite AC power to all 4KV Vital Buses AND? 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: Prolonged loss of off-site AC power reduces required redundancy and potentially degrades the level of safety of the plant by rendering the plant more vulnerable to a complete loss of AC power to eme.geRGy-vital busses.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of off-site power.Explanation/Discussion/Definitions:

The AC power distribution is summarized in Attachment 2, page 2.Emergency Classification escalates to an ALERT under EAL SA1.1 based on AC power to 4KV vital buses being reduced to a single source.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -SUW Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram Salem Page 1 of 2 Rev. 0 (draft E)EAL#: SU 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1 A.C. Sources 7. SGS Technical Specifications 3.8.2 Onsite Power Distribution Systems 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10. S1(S2).OP-AB.LOOP-0001(Q)

Loss of Off-Site Power 11. S1(S2).OP-AB.4KV-0001 (Q) Loss of 1A(2A) 4KV Vital Bus 12. SI (S2).OP-AB.4KV-0002(Q)

Loss of 1 B(2B) 4KV Vital Bus 13. S1(S2).OP-AB.4KV-0003(Q)

Loss of 1 C(2C) 4KV Vital Bus Salem Page 2 of 2 Rev. 0 (draft E)EAL#: SUl .1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: S -System Malfunction 1 -Loss of AC Power AC power capability to vital buses reduced to a single power source for 15 minutes or longer such that any additional single failure would result in complete loss of AC power to vital buses 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SAI.1 -ALERT EAL: Loss of 4KV Vital Bus Power Sources (Offsite and Onsite) which results in the availability of only one 4KV Vital Bus Power Source (Offsite or Onsite)AND 2! 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: rThS t1Q a~e/ the aSGo.iated E.. ,4Ls a intende,,d to ...de an .....o. 1G ,- ., ,ss of All ("')H- ;in AO"

,... Q3 IF^~c f,- rý- "Tl -f:AZ A A -,,÷ .4, The condition indicated by this tG-EAL is the degradation of the off-site and on-site AC power systems such that any additional single failure would result in a complete loss of AC power to vital busesstation blackout.

This condition could occur due to a loss of off-site power with a concurrent failure of all but one emergency diesel generator to supply power to its emefgep~y vital busses. Another .latod condition, c9uld be the loss of a. l off site power and loss of on site oamarmnna d~i --I -~ '+~c -~ l~ rk,4r.-ýns ihen n t r_-inn romar ant- ki~ ,tcon kninr fnAr frnrs pff;;jt ~tS.S tAttSttt~

~ S) ~JS~ t~t S ~t. 1.Z' J 1-3 Y ýj nA/gZr kn A frnrn jhp i ini+ rnpin =r-,s=rn+nr nr finn lrL-L- nf rAn c,;+- ýmnr nnn A; i t,. I) ASf-S.i. t .i LtS tIt t 51 IýJ3 tt. 45/ ' 11.I)st 01 .t .)tjyltStI S/ S.) S.iS).S In prn+r nr %.il+h ý',lj, ^-p +r~r ,f -k cc~c k 1~-r ; f A k [,-F A -F ff, ;+, iL~ .ISi / t)11 S)S ~~t .J .ItS ~St 14 .SSS/S//JSI

~t~lA .SA.tI/A I 1/ I5/iStt.The subsequent loss of this single power source would escalate the event to a SITE AREA EMERGENCY in accordance with EAL SS1.1.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of power.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: SA 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213[At m~ulti unit statons-, tMe EA4L& shouldf ageow credit for- operation of installed design featUreS-, such as Gross ties o~r sKing diesels, provided that abnormal or emergency4 operating p,,cedur-, address thi use. these stations mu,,stals

.,onsd.v t,,v impat of thi-condition on other shaICd saeto fincutions in developing the site specii E-AL[Plants that have a Procedur-al~ed capabifity to croess tie A Gpo wer fro9m an off site-power-supplyof a omninunit may take Glodit for- the redundant power- source in the associa ted EA-L fet: tNi--IC.ExplanationIDiscussion/Definitions: "Availability" means the power source can be aligned to provide power to a vital bus within 15 minutes or is currently supplying power to at least one vital bus.The availability of EDGs that have not been challenged to start during degradation of AC power sources to the 4KV vital buses should be based on meeting Technical Specification action requirements for loss of offsite AC power sources.The AC power distribution is summarized in Attachment 2, page 2.This hot condition Alert EAL is equivalent to the cold condition Unusual Event EAL CUi.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -SA5 Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1 A.C. Sources 7. SGS Technical Specifications 3.8.2 Onsite Power Distribution Systems 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10. S1 (S2).OP-AB.LOOP-0001 (Q) Loss of Off-Site Power 11. S1(S2).OP-AB.4KV-0001(Q)

Loss of 1A(2A) 4KV Vital Bus 12. S1(S2).OP-AB.4KV-0002(Q)

Loss of 1B(2B) 4KV Vital Bus 13. S1(S2).OP-AB.4KV-0003(Q)

Loss of 1C(2C) 4KV Vital Bus Salem Page 2 of 2 Rev. 0 (draft E)EAL#: SA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 1 -Loss of AC Power Loss of all offsite power and all onsite AC power to vital buses for 15 minutes or longer 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SS1.1 -SITE AREA EMERGENCY Loss of all Power (Onsite and Offsite) to all 4KV Vital Buses AND_ 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: Loss of all AC power to emeFgeney-vital busses compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal and the Ultimate Heat Sink (Service Water). Prolonged loss of all AC power to emergenGy-vital busses will lead to loss of Fuel Clad, RCS, and Containment, thus this event can escalate to a GENERAL EMERGENCY.

Fifteen minutes was selected as a threshold to exclude transient or momentary losses of off-site power.rAt y, ,ip , ,irtiun -Q'f'i* rc' thin F-Al c- obup jzinCItiAi irmtr~iU frir ~ ,. b-- F~ I,- C-pht f r nf ,rC'V LIIlL.llLl tAt lit LALS~4tl'.fl 11.1, LI 1L L...# 11. LA LAIILLAILA LAIILJVV '...'.A It ItJI L4t,~LAl I."I I-f, , WIS Al t11Hhg OIt f, G-- p-U fHL ...pb_; .; g .--1, r ,l;r mei .t -. rge, I,,c'i,. " I- , I&L17LLIALLAAtlil IAL 141 IV IL II. LIL LALLIA -~ -- I-M rrTrr 0~ "4LL UCIA "LI I TV conditio on other sharedl safety functions in dceý!Gpipg the &~ePecifiGcEAL]-" i Iiii.rr-)t- -i.- i-t,-4 t- ---1;- 4 ---- 1,;1;,k , 4 A /- ---4C -;,--It.'S I.ItI ~ I I m' itI4LSIIIS.A1A fISAJ I~J tA.IL.tI.

IL IS~m L'AVtI Idul al .-l LII-Ifr'Lmm-A

'I~LI&IZ I) Lt L -~lIIS.lI

.1IL it IIL ~ 5.114 LIL AI i EAL fF -thi&I-4 Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SSI .1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 Escalation to GENERAL EMERGENCY is via EALs in Category F, Fission Product Barrier Degradation, or WEAL SGI.1, "Prolonged Loss of All Off-site Power and Prolonged Loss of All On-site AC Power." Explanation/Discussion/Definitions:

The intent of this EAL is to classify degraded AC power events that result in a loss of all offsite 13.8 KV power sources to the 4KV vital buses along with a loss of all onsite power sources (EDGs).The AC power distribution is summarized in Attachment 2, page 2.This hot condition Site Area Emergency EAL is equivalent to the cold condition Alert EAL CA1.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -SS1 Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1 A.C. Sources 7. SGS Technical Specifications 3.8.2 Onsite Power Distribution Systems 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10. S1(S2).OP-AB.LOOP-0001 (Q) Loss of Off-Site Power 11. S1(S2).OP-AB.4KV-0001(Q)

Loss of 1A(2A) 4KV Vital Bus 12. S1 (S2).OP-AB.4KV-0002(Q)

Loss of 1 B(2B) 4KV Vital Bus 13. S1 (S2).OP-AB.4KV-0003(Q)

Loss of 1 C(2C) 4KV Vital Bus Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SSl.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SSI.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 1 -Loss of AC Power Prolonged loss of all offsite and all onsite AC power to vital buses 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown EAL# & Classification Level: SGI.1 -GENERAL EMERGENCY EAL: Loss of all Power (Onsite and Offsite) to all 4KV Vital Buses AND EITHER of the following:

Restoration of at least one Vital Bus in < 4 hrs is NOT likely* CFST Core Cooling RED or PURPLE path exists Basis: Loss of all AC power to emergeRGy-vital busses compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal and the Ultimate Heat Sink (Service Water). Prolonged loss of all AC power to emergency-vital busses will lead to loss of Fuel Clad, RCS, and Containment, thus this event can escalate to a GENERAL EMERGENCY.

[The (sGite specific hour-s) to AC power cap be based on a Sit,, kolut G-pi, g ana-,sis;;; l; ;;; f-ý 1 ;;; ;;;_;; -.1',; ; ......V .,v=F , ..,.,,,.. -!ytU r ; nLy. ;. ;1 L; ou L;,;------- ----------C:1 f-1 auF"!rr)!pdinr aneasc s~hould he annizderd Although this 1f mayi be viewei'd as Fdundapt fr) fi Y 11ý1 " --- .---I --f-f U-1-1 I -I -.-- -r, r-t- Cr'-y'-'ttt-y t-T y -........;-t""t ......u; -, ;u u;;;!; y ; tibu ;b-"-,b This -G-EAL is specified to assure that in the unlikely event of a prolonged station blackout, timely recognition of the seriousness of the event occurs and that declaration of a GENERAL EMERGENCY occurs as early as is appropriate, based on a reasonable assessment of the event trajectory.

Salem Page 1 of 5 Rev. 0 (draft E)EAL#: SG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 The likelihood of restoring at least one bus should be based on a realistic appraisal of the situation since a delay in an upgrade decision based on only a chance of mitigating the event could result in a loss of valuable time in preparing and implementing public protective actions.In addition, under these conditions, fission product barrier monitoring capability may be degraded.Salem Page 2 of 5 Rev. 0 (draft E)EAL#: SG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213[Although it m~ay be diffiGuO to p r,-diJt When power- Gan be r-eto~eljj dit is no cessarý" to give the EmergenG,,y based on two majoFr

1. Are there any present /indiations that " ore coling i& akready degraded to the point tha loe s or potential loss Fisui zen duct i rtchent 2 pe2NT?2. if there arc no present indications Of SUch Gore .OoA43g degradaton, how likey s it that pr ed powe restof inv tier a ssure thaals of twi AC pow potential 1or the third baorrieter canin barrier ossented?Thue, indicatiho of roetoruing core cooling degradation must be based on a ission praodut sati~eF onsite~ng aeyn upgrade ecis on O n only Directer judgment as it relate t IMMINEsNT s loss o ptential los Of fission prpdugt barnrierms and degraded ablity to Metito I infission product barrier Explanation/Discussion/Definitions:

The AC power distribution is summarized in Attachment 2, page 2.Four hours is the station blackout coping time.The status and availability of DC power may limit or prevent restoration activities.

When prolonged powering of inverters and DC loads has occurred without AC power available for the battery chargers, DC voltage will degrade. This degradation of DC power may limit monitoring and assessment capabilities as instrumentation and control power may not be available.

Since monitoring of overall plant conditions will be difficult with no AC power, CFST indications for determining barrier loss are used.The likelihood of restoring at least one Vital Bus should be based on a realistic appraisal of the situation since a delay in an upgrade decision based on only a chance of mitigating the event could result in a loss of valuable time in preparing and implementing public protective actions.In addition, under these conditions, fission product barrier monitoring capability may be degraded.

Although it may be difficult to predict when power can be restored, it is necessary to give the Emergency Coordinator reasonable idea of how quickly he may need to declare a General Emergency based on two major considerations:

1. Are there any present indications that core cooling is already degraded to the point that loss or potential loss of fission product barriers is imminent?2. If there are no present indications of such core cooling degradation, how likely is it that power can be restored in time to assure that a loss of two barriers with a potential loss of the third barrier can be prevented?

It is estimated that several hours are required to fully evacuate the 1 0-mile EPZ. Taking into consideration the above factors, declaring a General Emergency leaves sufficient time for the offsite authorities to implement Protective Actions well before a radioactive release would Salem Page 3of 5 Rev. 0 (draft E)EAL#: SGI .1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 occur while providing sufficient time for on-site and off-site mitigation activities to restore AC power.CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs. The Core Cooling CFST is illustrated in Attachment 2, page 4.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -SG1 Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1 A.C. Sources 7. SGS Technical Specifications 3.8.2 Onsite Power Distribution Systems 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10. S1 (S2).OP-AB.LOOP-0001 (Q) Loss of Off-Site Power 11. S1 (S2).OP-AB.4KV-0001 (Q) Loss of 1A(2A) 4KV Vital Bus 12. S1 (S2).OP-AB.4KV-0002(Q)

Loss of 1 B(2B) 4KV Vital Bus 13. SI (S2).OP-AB.4KV-0003(Q)

Loss of 1 C(2C) 4KV Vital Bus-1-214.UFSAR 3.12.1.1 Conformance to NRC Rule on Station Blackout 4-315.ES-45.003(Q)

Station Blackout Duration Calculation-I-416.1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 2 Core Cooling Status Tree 4-517.PSE&G Emergency Operating Procedure Setpoint Document Salem Units 1 & 2 Salem Page 4 of 5 Rev. 0 (draft E)EAL#: SG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-213 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: SG 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-214 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 2 -Loss of DC Power Loss of all vital DC power for 15 minutes or longer 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SS2.1 -SITE AREA EMERGENCY< 114 VDC bus voltage indications on All 125 VDC vital buses for _ 15 minutes (Note 3)OR< 25 VDC bus voltage indications on both 28 VDC vital buses for _ 15 minutes (Note 3) AND loss of control of Safety Related Equipment from the Control Room has been confirmed Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: Loss of all DC power compromises ability to monitor and control plant safety functions.

Prolonged loss of all DC power will cause core uncovering and loss of containment integrity when there is significant decay heat and sensible heat in the reactor system.oc;*n __;c;_ k'f,r' ý C ,,-4I,-, e,- , ,i,-,i A kI-n -- ~n/ fln -,h--r n A-, n rInini'i ne -,r-,, the oper-ation-of safety related equipment.

This voltage value should incorpor-ate a mar~gin of at least 15 minutes of ,peri,;at be-fre the onset of inability to operate those leads. This olhtage is usuagy near the minimum voltage selected when batter sizi i's peormed.Tiy value for- the entie batthyý set tisappr-oxina tely 105 VDC. F=or az 40 cell string onf batteries the cell voltacoG is 4voicalv 1. 7-5 Volfts aer cell. F-or a 58 sftrinG batteryv set the minium voGltace i Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Escalation to a General Emergency would occur by EALs in Category R, Abnormal Rad Levels/Radielegical Effluent, or Category F, Fission Product Barrier Degradation.

Explanation/Discussion/Definitions:

Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SS2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-214 The specified bus voltage indications (rounded for readability on Control Room instrumentation) are the minimum voltage requirements for operability of the 125 VDC buses and 28 VDC buses following battery discharge tests. Although continued operation may occur with degraded voltage, these values signify the minimum operable voltages allowed.This Site Area Emergency EAL is the hot condition equivalent of the cold condition loss of DC power Unusual Event EAL CU2.1.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SS2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-214 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SS3 Example EAL #1 2. SC.MD-ST.125-0004 (Q) 125 Volt Station Batteries 18 Month Service Test and Associated Surveillance Testing Using BCT-2000 3. SC.MD-ST.28D-0004 (Q) 28 Volt Station Batteries 18 Month Service Test and Associated Surveillance Using BCT-2000 4. UFSAR 8.3.2 DC Power 5. SGS Technical Specifications 3.8.2.3 125 Volt DC Distribution

-Shutdown 6. SGS Technical Specifications 3.8.2.5 28 Volt DC Distribution

-Shutdown 7. S1($2).OP-SO.125-0005 1(2)A 125VDC Bus Operation 8. S1($2).OP-SO.125-0006 1(2)B 125VDC Bus Operation 9. S1($2).OP-SO.125-0007 1(2)C 125VDC Bus Operation Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SS2.1

SGS ECG -EAL Technical Bases EP-SC-1 11-215 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 3 -ATWT / Criticality Inadvertent Criticality 3 -Hot Standby, 4 -Hot Shutdown EAL# & Classification Level: SU3.1 -UNUSUAL EVENT EAL: UNPLANNED sustained positive startup rate observed on nuclear instrumentation Basis: This EAL addresses inadvertent criticality events. This ,-0-EAL indicates a potential degradation of the level of safety of the plant, warranting a NQUE classification.

This tO-EAL excludes inadvertent criticalities that occur during planned reactivity changes associated with reactor startups (e.g., criticality earlier than estimated).

[This c-ndition cGa be idetified ung pe.iod monitorsstartup rate monitor-.

The term Escalation would be by the Fission Product Barrier Table, as appropriate to the operating mode at the time of the event.Explanation/Discussion/Definitions:

The term "sustained" is used in order to allow exclusion of expected short term positive startup rates from planned fuel bundle or control rod movements during core alteration.

These short term positive startup rates are the result of the increase in neutron population due to subcritical multiplication.

Positive reactor startup rate may be identified by: t Source range startup rate indicators NI31 D and NI32D* NIS Recorder NR45* Audio count rate* SPDS" Process Computer Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 This EAL is the hot condition equivalent of the cold condition EAL CU6.1.Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 EAL Bases Reference(s):

1.2.3.4.5.NEI 99-01, Rev. 05, SU8 Example EAL #1 Technical Specifications 3.3.1.1 Reactor Trip System Instrumentation UFSAR Table 7.5-2 Main Control Room Indicators and/or Recorders Available to Plant Operators to Monitor Significant Plant Parameters During Normal Operations SC.IC-CC.NIS-001 1(Q) N31 Source Range SC.IC-CC.NIS-0012(Q)

N32 Source Range Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SU3.1 SGS ECG -EAL Technical Bases EP-SC- 111 -215 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 3 -ATWT / Criticality Automatic trip fails to shut down the reactor and the manual actions taken from the reactor control console are successful in shutting down the reactor 1 -Power Operations, 2 -Startup EAL# & Classification Level: SA3.1 -ALERT EAL: An automatic trip failed to shut down the reactor AND Manual trip actions taken at the reactor control console (reactor trip switches, trip bkr bezels, supply breakers 1/2E6D and 1/2G6D) successfully shut down the reactor as indicated by reactor power < 5%Basis:[The reactor should be considered shutdown when it producing less heat than the maximum decay heat load for which the safety systems are designed (typ'Gally, 3 tE-5% power). F-oe..CSFSTs, tThis EAL equates to the criteria used to determine a valid CFST Su,,oitioality-,Shutdown Margin Red Path. For BWRs this EAL should be the ,APRM dGWnscale trip sctpeint-.]

Manual soram-(trip) actions taken at the reactor control console are any set of actions by the reactor operator(s) which causes or should cause control rods to be rapidly inserted into the core and shuts down the reactor........he manual.s.r.reactor trip) switchespushb.utte on the Ceontrol Rroom console....are ...sidered-an automatic input into the Reactor Protection System-a.

A failure to scram-(trip) after actuating both reactor trip switches without any other automatic input would make this threshold applicable.][MCD1]

This condition indicates failure of the automatic protection system to scram-(trip) the reactor.This condition is more than a potential degradation of a safety system in that a front line automatic protection system did not function in response to a plant transient.

Thus the plant safety has been compromised because design limits of the fuel may have been exceeded.

An ALERT is indicated because conditions may exist that lead to potential loss of fuel clad or RCS and because of the failure of the Reactor Protection System to automatically shutdown the plant.Salem Page 1 of 4 Rev. 0 (draft E3)EAL#: SA3.M SGS ECG -EAL Technical Bases EP-SC-1 11-215 If manual actions taken at the reactor control console fail to shut-down the reactor, the event would escalate to a SITE AREA EMERGENCY.

Explanation/Discussion/Definitions:

This EAL identifies the need to cease critical reactor operations by actuation of the automatic Reactor Protection System (RPS) trip function.

A reactor trip is automatically initiated by the Reactor Protection System (RPS) when certain continuously monitored parameters exceed predetermined setpoints.

Following a successful reactor trip, rapid insertion of the control rods occurs. Nuclear power promptly drops to a fraction of the original power level and then decays to a level several decades less with a negative period. The reactor power drop continues until reactor power reaches the point at which the influence of source neutrons on reactor power starts to be observable.

A predictable post-trip response from an automatic reactor trip signal should therefore consist of a prompt drop in reactor power as sensed by the nuclear instrumentation and a lowering of power into the source range. A successful trip has therefore occurred when there is sufficient rod insertion from the trip of RPS to bring reactor power to below 5%, the value used to determine a valid Shutdown Margin Status Tree Red Path. CSFST Shutdown Margin red path is illustrated in Attachment 2, page 5.For the purposes of emergency classification at the Alert level, successful manual trip actions are those which can be quickly performed from the reactor control console (i.e., reactor trip switches, trip bkr bezels, supply breakers 1/2E6D and 1/2G6D). EOP-FRSM-1 requires an Equipment Operator to locally open the Reactor Trip Breakers and trip the Rod Drive MG Sets. These actions are performed outside the Main Control Room and are NOT to be credited as a successful manual trip.Following any automatic RPS trip signal EOPs prescribe insertion of redundant manual trip signals to back up the automatic RPS trip function and ensure reactor shutdown is achieved.Even if the first subsequent manual trip signal fully inserts all control rods immediately after the initial failure of the automatic trip, the lowest level of classification that must be declared is an Alert.In the event that the operator identifies a reactor trip is imminent and initiates a successful manual reactor trip before the automatic trip setpoint is reached, no declaration is required.The successful manual trip of the reactor before it reaches its automatic trip setpoint or reactor trip signals caused by instrumentation channel failures do not lead to a potential fission product barrier loss.If manual reactor trip actions fail to reduce reactor power below 5%, the event escalates to the Site Area Emergency under EAL SS3.1.If by procedure, operator actions include the initiation of an immediate manual trip following receipt of an automatic trip signal and there are no clear indications that the automatic trip failed (such as a time delay following indications that a trip setpoint was exceeded), it may be Salem Page 2 of 4 Rev. 0 (draft E3)EAL#: SA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -215 difficult to determine if the reactor was shut down because of automatic trip or manual actions.If a subsequent review of the trip actuation indications reveals that the automatic trip did not cause the reactor to be shut down, consideration should be given to evaluating the fuel for potential damage, and the reporting requirements of 10CFR50.72 should be considered for the transient event.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SA2 Example EAL #1 2. UFSAR 7.1.1.1 Reactor Trip Systems 3. UFSAR Table 7.2-1 List of Reactor Trips, Engineered Safety Features, Containment and Steam Line Isolation and Auxiliary Feedwater 4. Technical Specifications Table 3.3-1 Reactor Trip System Instrumentation

5. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 6. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 1 Shutdown Margin Status Tree 7. 1(2)-EOP-FRSM-1 Response to Nuclear Power Generation Salem Page 3 of 4 Rev. 0 (draft E3)EAL#: SA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E3)EAL#: SA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 3 -ATWT / Criticality Automatic trip fails to shut down the reactor and manual actions taken from the reactor control console are not successful in shutting down the reactor.1 -Power Operations, 2 -Startup SS3.1 -SITE AREA EMERGENCY An automatic trip failed to shut down the reactor AND Manual trip actions taken at the reactor control console (reactor trip switches, trip bkr bezels, supply breakers 1/2E6D and 1/2G6D) do NOT shut down the reactor as indicated by reactor power > 5%Basis: fThe reactor should be considered shutdown when it-producing less heat than the maximum decay heat load for which the safety systems are designed (typially-3 te-5% power). F-ef plants using CSFSTs, tThis EAL equates to the criteria used to determine a valid CFST Sub,.iti.alit,-Shutdown Margin Red Path. For BWRs this EAL should be the APRM downscale trip Setpoin÷t.]

Under these conditions, the reactor is producing more heat than the maximum decay heat load for which the safety systems are designed and efforts to bring the reactor subcritical are unsuccessful.

A SITE AREA EMERGENCY is warranted because conditions exist that lead to IMMINENT loss or potential loss of both fuel clad and RCS.[T ,Q=-afa Ch ljdh. anc~l~ ýh t P=. zPPLPPP itn.....'-a S ea ta te a .4ALAALA knP ILALAL fnAAP. PLAP VSt- Sill LI ý~t- tem a= LAP..ILAd LA,)PALLA 2 toA "A I.,LALLA JPLPL.YAIPL F LPPP) P aINI LP L A I IP APr Lr.tft ALAL S IPL A LIIL IAAA L. AAL 0 14 LA fL IP A IA LI L .AI LA LAALALLAIPL ll ILIIL LAic iEA ln " li fI LALAL fP i cLTI7 nt'pi nJJ'if I V7 cr .r- CT Manual scram(trip) actions taken at the reactor control console are any set of actions by the reactor operator(s) at which causes or should cause control rods to be rapidly inserted into the core and shuts down the reactor. I h /I ..... I.-.-X --: --.-. .1-. 4.-I- ---I ,~PP~ 4 P- I f I~, -I EvianuI u~ i ii U IH kL lid) dbHViI ib C H t U -11 LA..... .AI-LA--U -A'LLAAIA PPa W! LAPLI cifu iti P! t P) HIPI U 1Vt;tV cotrol console i's required to scram (triD) the reactor. This EAL is still aD~!icable even it% I /I Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SS3.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -215 actions tALke away fronm the reactor cortrol cgnsole are successful in shuting the feactor down because the destigr limits ef the fuel may have bpen exceeded or bexaus of the groaS failuer of the Reactor Protection System te shutidow the plan Fortheugh tris 1G emyergency cassifedidant to the FSite AreProduct 9 eae, successfuC its in~ui "-I ----t betteF assur-e M44e a F6GgtO fand ep 4 eg6ý at-v-sarr Escalation of this event to a GENERAL EMERGENCY would be due to a prolonged condition leading to an extreme challenge to either core-cooling or heat removal.Explanation/Discussion/Definitions:

This EAL addresses any automatic reactor trip signal followed by a manual trip that fails to shut down the reactor to an extent the reactor is producing energy in excess of the heat load for which the safety systems were designed.For the purposes of emergency classification at the Site Area Emergency level, successful manual trip actions are those which can be quickly performed from the reactor control console (i.e., reactor trip switches, trip bkr bezels, supply breakers 1(O)E6D and 1(r)G6D).

EOP-FRSM-1 requires an Equipment Operator to locally open the Reactor Trip Breakers and trip the Rod Drive MG Sets. These actions are performed outside the Main Control Room and are not to be credited as a successful manual trip.For emergency classification purposes, the reactor should be considered shutdown when it is producing less heat than the maximum decay heat load for which the safety systems are designed.

This equates to < 5% power, the value used to determine a valid Shutdown Margin Status Tree Red Path. CSFST Shutdown Margin red path is illustrated in Attachment 2, page 5.Entry into EOP-FRSM-1 will be required if the manual trip from the console "trip handles" or Turbine Trip and P-9 (2: 49% Power) is not successful.

EOP-FRSM-1 requires an Equipment Operator to locally open the Reactor Trip Breakers and trip the Rod Drive MG Sets. Since this action is outside the Control Room, a successful remote Reactor Trip will still require classification under this EAL because the design limits of the fuel may have been exceeded or because of the gross failure of the RPS to shut down the plant. The threshold value of < 5%reactor power was selected to be consistent with CFST EOP-FRSM-1 entry criteria.

Mode 2 is included in this EAL to include events which result in a return to > 5% reactor power from some lower value.Escalation of this event to a GENERAL EMERGENCY would be under EAL 5G3.1 or Emergency Coordinator judgment.Definitions:

Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SS3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SS2 Example EAL #1 2. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 3. 1(2)-EOP-FRSM-1 Response to Nuclear Power Generation

4. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 1 Shutdown Margin Status Tree Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SS3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-215 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 3 -ATWT / Criticality Automatic trip and all manual actions fail to shut down the reactor and indication of an extreme challenge to the ability to cool the core exists 1 -Power Operations, 2 -Startup SG3.1 -GENERAL EMERGENCY An automatic trip failed to shut down the reactor AND All manual actions do NOT shut down the reactor as indicated by reactor power _> 5%AND EITHER of the following:

CFST Core Cooling RED path exists* CFST Heat Sink RED path exists due to actual loss of secondary heat sink and heat sink is required Basis:{The reactor should be considered shutdown when it producing less heat than the maximum decay heat load for which the safety systems are designed 3 '-,5% power). Fe;pkntS WSing CSFSTs, tThis EAL equates to the criteria used to determine a valid CFST&ibe,-;riti.eali, Shutdown Margin Red Path. BWRs this EAL should be the APRM dewRSG-e "~PipSt 7 3it.Under these conditions, the reactor is producing more heat than the maximum decay heat load for which the safety systems are designed and efforts to bring the reactor subcritical are unsuccessful.

r rhi ., if r .,?2:-in .! .--h .. ... ".-,rr 4,- 14~ 1,r,%-.I 0 IF. ICZ/ C_.A,~r r, inn 11 # 1 n 4 F-~r -A A It Si% -F- I IFplants u~siog CSF-ST", tis A' equ~ates to th7e Gtle! use ri dto doeterrnlne a vafid Subc-r~itiali

'ý-~~~~~ ~ ~ ~ ~ 1 i ."- ýv ft f ft M p, lJH'r]" "l .... I ....... J Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SG3.1 SGS ECG -EAL Technical Bases EP-SC-11 11-215PWRs, the .. tr...e Fhal,.. e to the ab.ity to Gool the core is intended to me.an that the corn exet it herfaturhes arc at oaapproaching 1200 degrees-F or that the reacto r vnessel wateb r lbelois below the top of actiVe fuet For spafts using ySFdST, thia s EmL equatecs toa Co.r Cooling RED GondWtion combined with a Subcr~ticait~y RED conditkio.]

[F-eF ~ ~ BRte,*me Ghage"g te t~e abi, to Gee! the GF- i- pe d to ~a that the[For Bsiuto, thre dxgradationg cnour railyo this creasn h EEA reactor vessel wateor- fe'J crannot berest~e and m~aintained above M4inimum Steam Cooling RPV Water Level as described in th e Pbss Mnother GENsideration is the inabtien to initia remove heat during te early stages of tha deqUeclt.

Fto Permif ema egxniu d 9 i uffiet t9ff-soit titr aeniotme heat required by design4 fromq at least one steam4 generator-, an ex e hallenge should be coqnsidered to exist. For- plants using CSF-ST-s, this EAL equates to a Heat Sink RED condition co)mbined Mit a SubG4t.'ca.

RE=D condition.]

[For- BWRs, consider-ations in cluedo :nabifity to removeý heat via the m~ain condenser-, or via the supprssio pool or- tor-us (e.g., due to high pool water tempernature)-.]

In the event either of these challenges exists at a time that the reactor has not been brought below the power associated with the safety system design., a core melt sequence exists. In this situation, core degradation can occur rapidly. For this reason, the GENERAL EMERGENCY declaration is intended to be anticipatory of the fission product barrier table declaration to permit maximum off-site intervention time.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SG3.1 SGS ECG -EAL Technical Bases EP-SC-11 11-215 Explanation/Discussion/Definitions:

For emergency classification purposes, the reactor should be considered shutdown when it is producing less heat than the maximum decay heat load for which the safety systems are designed.

This equates to < 5% power, the value used to determine a valid Shutdown Margin Status Tree Red Path. CSFST Shutdown Margin red path is illustrated in Attachment 2, page 5.Entry into EOP-FRSM-1 will be required if the manual trip from the console "trip handle" or Turbine Trip and P-9 (> 49% Power) is not successful.

EOP-FRSM-1 requires an Equipment Operator to locally open the Reactor Trip Breakers and trip the Rod Drive MG Sets. Since this action is outside the control room, a successful remote Reactor Trip will require classification under this EAL. The threshold value of 5% reactor power was selected to be consistent with CFST EOP-FRSM-1 entry criteria.

For events, which result in a return to > 5% reactor power from some lower value, classification under this EAL would be required.Further degradation is indicated by the occurrence of valid CFST Core Cooling red path or Heat Sink red path. The Core Cooling red path is indicative of a loss of core cooling and the Heat Sink red path of a potential loss of core cooling. CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs. CFST Core Cooling and CFST Heat Sink are illustrated in Attachment 2 page 4 and 6, respectively.

If the Heat Sink red path is due to a procedurally directed action, classification under this EAL is not required.

EOP-FRSM-1 directs the operators to minimize feedwater flow to the steam generators in order to minimize cooldown and control reactivity.

A heat sink red path is generated as a result of this operator action. However, actual loss of control of the heat sink does not occur due to these actions. In addition, the heat sink red path is precursor to a loss of core cooling and is backed up by the core cooling red path. Declaration of a General Emergency is not justified if the heat sink red path is a result of procedurally directed actions.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SG2 Example EAL #1 2. 1(2)-EOP-FRSM-1 Response to Nuclear Power Generation

3. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 4. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 1 Shutdown Margin Status Tree 5. PSE&G Emergency Operating Procedure Setpoint Document Salem Units 1 & 2 6. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 2 Core Cooling Status Tree 7. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -Figure 3 Heat Sink Status Tree Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SG3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-216 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 4 -Inability to Reach or Maintain Shutdown Conditions Inability to reach required shutdown within Technical Specification limits 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Shutdown EAL# & Classification Level: SU4.1 -UNUSUAL EVENT EAL: Plant is NOT brought to required operating mode within Technical Specifications LCO action statement time Basis: Limiting Conditions of Operation (LCOs) require the plant to be brought to a required operating mode when the Technical Specification required configuration cannot be restored.

Depending on the circumstances, this may or may not be an emergency or precursor to a more severe condition.

In any case, the initiation of plant shutdown required by the site Technical Specifications requires a four hour report under 10 CFR 50.72 (b) Non-emergency events. The plant is within its safety envelope when being shut down within the allowable action statement time in the Technical Specifications.

An immediate NOUE is required when the plant is not brought to the required operating mode within the allowable action statement time in the Technical Specifications.

Declaration of a NQUE is based on the time at which the LCO-specified action statement time period elapses under the site Technical Specifications and is not related to how long a condition may have existed.[Other- r-eq ure d TeGhnical SpecGification ShUtdewp&

that inole pmcr-sor-s to more GerIous e~nt _rc &'ddesed b~y other system4 M~alfunction, Haado Fission Prod~uct 9arrier De adation 106ýExplanation/Discussion/Definitions:

Depending on the circumstances, this may or may not be a precursor to a more severe condition.

A shutdown required by the Technical Specifications requires a report under 10 CFR 50.72 (b) non-emergency events. The plant is within its safety envelope when actions are completed within the allowable Action Statement time in the T/S. If the times specified within the Action Statements are not met, the plant may be in an unsafe condition.

EAL Bases Reference(s):

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: SU4.1 SGS ECG -EAL Technical Bases 1. NEI 99-01, Rev. 05, SU2 Example EAL #1 2. SGS Technical Specifications EP-SC-1 11-216 This page intentionally blank.Salem Page 2 of 2 Rev. 0 (draft E)EAL#: SU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 5 -Instrumentation UNPLANNED loss of safety system annunciation or indication in the Control Room for 15 minutes or longer 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown EAL# & Classification Level: SU5.1 -UNUSUAL EVENT EAL: UNPLANNED loss of > approximately 75% of Control Room Overhead Annunciators for_> 15 minutes (Note 3)OR UNPLANNED loss of > approximately 75% of Control Room Indications associated with the following safety functions for _ 15 minutes (Note 3):* Reactivity Control" RCS Inventory" Decay Heat Removal* Fission Product Barriers Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: This IC ;and its associated EAL are-is intended to recognize the difficulty associated with monitoring changing plant conditions without the use of a major portion of the annunciation or indication equipment.

Recognition of the availability of computer based indication equipment is

& -1ap, L ý,e, o-mute-,et.."Planned" loss of annunciators or indicators includes scheduled maintenance and testing activities.

Salem Page 1 of 5 Rev. 0 (draft E)EAL#: SU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 Quantification is arbitrary, however, it is estimated that if approximately 75% of the safety system-annunciators or indicators are lost, there is an increased risk that a degraded plant condition could go undetected.

It is not intended that plant personnel perform a detailed count of the instrumentation lost but use the value as a judgment threshold for determining the severity of the plant conditions.

It is further recognized that most plant designs provide redundant safety system indication powered from separate uninterruptible power supplies.

While failure of a large portion of annunciators is more likely than a failure of a large portion of indications, the concern is included in this EAL due to difficulty associated with assessment of plant conditions.

The loss of specific, or several, safety system indicators should remain a function of that specific system or component operability status. This will be addressed by the specific Technical Specification.

The initiation of a Technical Specification imposed plant shutdown related to the instrument loss will be reported via 10CFR50.72.

If the shutdown is not in compliance with the Technical Specification action, the NQUE is based on SU4.12 "Inability to Reach Required Shutdown Within Technical Specification Limits."[Site specific annUnciatOr-S OF indicator-s for this E-AL mus4t in dude those identified in the Abne-mal Op erating PRoc~durns, in the E-rnergeqcy Op er~a4ig ORe sedUrno and in ether- E,41=(e.g., area, p.eces, and/or. effluent rad moniters, etc.)..Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.[Due to the imitedl number of safty systes in oper-aten durng cold shutdown, rFefuegng;, and do fueled modes, PG 1C iS indicated during these modles of operation.]

This NOUE will be escalated to an ALERT based on a concurrent loss of compensatory indications or a SIGNIFICANT TRANSIENT is occurring during a loss of annunciators/indications.

[Other r ,,iv Technic/ e,,.'. ,fiatiG 81,÷4 that p to 3 .-I events are addressedf by other System Malfunction, Hazards, or FiýSsion ProGduct Bare, Doegradation

!Gs.]Explanation/Discussion/Definitions:

This EAL recognizes the difficulty associated with monitoring changing plant conditions without the use of a major portion of the annunciation or indication equipment.

A UNPLANNED loss of most or all Control Room Overhead Annunciators or other key control room safety function indicators without a plant transient in MODES 1, 2, 3, or 4 for > 15 minutes warrants a heightened awareness by Control Room Operators.

Quantification of> 75% is left to the discretion of the Shift Manager (SM), and is considered approximately 75%. It is not intended that a detailed count be performed, but that a rough approximation be used to determine the severity of the loss.OP-AB.ANN-0001 (Q) details increased monitoring and surveillance requirements as well as alternate indicators.

15 minutes is used as a threshold to exclude transient or momentary Salem Page 2 of 5 Rev. 0 (draft E)EAL#: SU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 power losses. The 15 minutes clock starts when the annunciators or other key Control Room safety function indications have been lost, or are determined to have been lost. If upon time of discovery it is determined that the annunciators or key safety function indications have been lost for at least 15 minutes prior to discovery, classification should be made under this EAL regardless of time required for restoration.

If it is determined that the annunciators were lost for at least 15 minutes with the annunciators now available at the time of discovery, classification is not required under this EAL, but a review of the "After The Fact" RAL (11.6)should be completed.

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: SU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -217 Definitions:

UNPLANNED:

a parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions. An UNPLANNED loss of annunciators and loss other key control room indication systems excludes scheduled maintenance and testing activities.

SIGNIFICANT TRANSIENT:

An UNPLANNED event based on EC judgment, but includes as a minimum any one of the following:

(1) automatic turbine runback greater than 25% thermal reactor power, (2) electrical load rejection greater than 25% full electrical load, (3) Reactor Trip, or (4) Safety Injection Activation.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SU3 Example EAL #1 2. SI(S2).OP-AB.ANN-0001(Q)

Loss of Overhead Annunciator System 3. UFSAR 7.7.2.10 Plant Alarm and Annunciator Systems 4. UFSAR Table 7.7-2 Overhead Annunciator Groupings Salem Page 4 of 5 Rev. 0 (draft E)EAL#: SU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: SU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: S -System Malfunction 5 -Instrumentation UNPLANNED loss of safety system annunciation or indication in the Control Room with either (1) a SIGNIFICANT TRANSIENT in progress, or (2)compensatory indicators unavailable 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SA5.1 -ALERT EAL: UNPLANNED loss of > approximately 75% of Control Room Overhead Annunciators for> 15 minutes (Note 3)OR UNPLANNED loss of > approximately 75% of Control Room Indications associated with the following safety functions for > 15 minutes (Note 3): " Reactivity Control* RCS Inventory* Decay Heat Removal* Fission Product Barriers AND EITHER of the following:

A SIGNIFICANT TRANSIENT is in progress, Table S-1* Compensatory indications are NOT available per OP-AB.ANN-0001(Q)

Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: SA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 Table S-1 SIGNIFICANT TRANSIENTS

Automatic turbine runback > 25% thermal reactor power* Electrical load rejection

> 25% full electrical load* Reactor Trip* Safety Injection Activation Basis: This IrG-EAL is intended to recognize the difficulty associated with monitoring changing plant conditions without the use of a major portion of the annunciation or indication equipment during a SIGNIFICANT TRANSIENT....... #=! ..... !/= =.#-v-eGccgituor Gf the~ aývH-&VIa:.

G1- GGP~r U- :r4uPvn uuJPm -:.q PIsu~oz C' M n L- -I- -4, -- --4-- 1, -,1- 1 1-, --, t, -I I -I It, -, Y --J .J"Planned" loss of annunciators or indicators includes scheduled maintenance and testing activities.

Quantification is arbitrary, however, it is estimated that if approximately 75% of the-safety system annunciators or indicators are lost, there is an increased risk that a degraded plant condition could go undetected.

It is not intended that plant personnel perform a detailed count of the instrumentation lost but use the value as a judgment threshold for determining the severity of the plant conditions.

It is also not intended that the Shift Super4pseF-Manager be tasked with making a judgment decision as to whether additional personnel are required to provide increased monitoring of system operation.

It is further recognized that most plant designs provide redundant safety system indication powered from separate uninterruptible power supplies.

While failure of a large portion of annunciators is more likely than a failure of a large portion of indications, the concern is included in this EAL due to difficulty associated with assessment of plant conditions.

The loss of specific, or several, safety system indicators should remain a function of that specific system or component operability status. This will be addressed by the specific Technical Specification.

The initiation of a Technical Specification imposed plant shutdown related to the instrument loss will be reported via 10 CFR 50.72. If the shutdown is not in compliance with the Technical Specification action, the NQUE is based on SkJ2-SU4.1 "Inability to Reach Required Shutdown Within Technical Specification Limits." rnu-r- ;- r- A I 1 -14 :- -1. 1-J- J-L- --- ;-J- -4;4- ýJ I- J.L- -.... JN ........ UJ JB L .. .--ý i f h r F n ri c ~ r w ir t i r L i~, ' ~ i id -r it '- TA 7 ý k I T F I T -F T '40'. ----~- -- 3~** 03 FM ra*-1 O~*** 4Prnp ,I- -d n*ý 1=4 741 11nor OpPrAtino (c~g, ara, eocc-, and,'orffluept rad mon 1'toFm, e c).Salem Page 2 of 5 Rev. 0 (draft E)EAL#: SA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217"Compensatory indications" in this context includes computer based information such as the pfGGess-Plant CeomputerSsystem and SPDS (see OP-AB.ANN-0001 (Q)).

include all ..systems avaiable for this use dcped..g on Spec.ifi design an.

re,.,fits.

If both a major portion of the annunciation system and all computer monitoring are unavailable, the ALERT is required.[Due to the limited numnber of safety system-s in opera~o t~id;Ir-hg cold shutdown, refueling and modes, no IG is indicated deuing thse modes of opefation.]

Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.This ALERT will be escalated to a SITE AREA EMERGENCY if the operating crew cannot monitor the transient in progress due to a concurrent loss of compensatory indications with a SIGNIFICANT TRANSIENT in progress during the loss of annunciation or indication.

[QthF Fquiec Te~n~al SeiiainshutdfownsMa involve prGFSF te rnr er.94 events are addressed by, othcr System M~alfuntion, Hazards, or F-ission ProdGuct Ba~rrio Degradation ICG.]Explanation/Discussion/Definitions:

OP-AB.ANN-0001(Q) details increased monitoring and surveillance requirements as well as alternate indicators during a loss of Control Room Overhead Annunciators.

The 15 minute clock starts when the annunciators or other key control room safety function indications have been lost, or are determined to have been lost. If upon time of discovery it is determined that the annunciators or key safety function indications have been lost for at least 15 minutes prior to discovery, classification should be made under this EAL regardless of time required for restoration.

SIGNIFICANT TRANSIENTS are listed in Table S-1 and include response to automatic or manually initiated functions such as reactor trips, automatic turbine runback greater than 25%thermal reactor power, electrical load rejection greater than 25% full electrical load, or Safety Injection activation.

The Plant Computer System and Safety Parameter Display System (SPDS) serve as redundant indicators which may be utilized as compensatory measures in lieu of the Control Room Overhead Annunciators and Control Room indicators associated with safety functions.

The judgment of the Shift Manager should be used as the threshold for determining the severity of the plant conditions.

If the operating crew cannot monitor the transient in progress, the ALERT escalates to a SITE AREA EMERGENCY under EAL SS5.1.Definitions:

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: SA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 UNPLANNED:

a parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions. An UNPLANNED loss of annunciators and loss other key control room indication systems excludes scheduled maintenance and testing activities.

SIGNIFICANT TRANSIENT:

An UNPLANNED event based on EC judgment, but includes as a minimum any one of the following:

(1) automatic turbine runback greater than 25% thermal reactor power, (2) electrical load rejection greater than 25% full electrical load, (3) Reactor Trip, or (4) Safety Injection Activation.

Salem Page 4 of 5 Rev. 0 (draft E)EAL#: SA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SA5 Example EAL #1 2. SI(S2).OP-AB.ANN-0001(Q)

Loss of Overhead Annunciator System 3. UFSAR 7.7.2.10 Plant Alarm and Annunciator Systems 4. UFSAR Table 7.7-2 Overhead Annunciator Grouping Salem Page 5 of 5 Rev. 0 (draft E)EAL#: SA5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 5 -Instrumentation Inability to monitor a SIGNIFICANT TRANSIENT in progress 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SS5.1 -SITE AREA EMERGENCY Loss of > approximately 75% of Control Room Overhead Annunciators for _ 15 minutes (Note 3)OR Loss of > approximately 75% of Control Room Indications associated with the following safety functions for _.15 minutes (Note 3):* Reactivity Control* RCS Inventory* Decay Heat Removal" Fission Product Barriers AND A SIGNIFICANT TRANSIENT is in progress, Table S-1 AND Compensatory indications are NOT available per OP-AB.ANN-0001 (Q)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Salem Page 1 of 5 Rev. 0 (draft E)EAL#: SS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -217 Table S-1 SIGNIFICANT TRANSIENTS" Automatic turbine runback > 25% thermal reactor power" Electrical load rejection

> 25% full electrical load* Reactor Trip" Safety Injection Activation Basis: This 4G-EAL is intended to recognize the threat to plant safety associated with the complete loss of capability of the control room staff to monitor plant response to a SIGNIFICANT TRANSIENT."Planned" and "UNPLANNED" actions are not differentiated since the loss of instrumentation of this magnitude is of such significance during a transient that the cause of the loss is not an ameI:atiEgra#_factor.

Quantification is arbitrary, however, it is estimated that if approximately 75% of the safet system-annunciators or indicators are lost, there is an increased risk that a degraded plant condition could go undetected.

It is not intended that plant personnel perform a detailed count of the instrumentation lost but use the value as a judgment threshold for determining the severity of the plant conditions.

It is also not intended that the Shift Supe..vise.

ManaQer be tasked with making a judgment decision as to whether additional personnel are required to provide increased monitoring of system operation.

It is further recognized that most plant designs provide redundant safety system indication powered from separate uninterruptible power supplies.

While failure of a large portion of annunciators is more likely than a failure of a large portion of indications, the concern is included in this EAL due to difficulty associated with assessment of plant conditions.

The loss of specific, or several, safety system indicators should remain a function of that specific system or component operability status. This will be addressed by the specific Technical Specification.

The initiation of a Technical Specification imposed plant shutdown related to the instrument loss will be reported via 10 CFR 50.72. If the shutdown is not in compliance with the Technical Specification action, the NOUE is based on S42-SU4.1 "Inability to Reach Required Shutdown Within Technical Specification Limits." A SITE AREA EMERGENCY is considered to exist if the Ceontrol R-foom staff cannot monitor safety functions needed for protection of the public while a significant transient is in progress.[Site spccific a~nnuniatorns for this EA4L §h7 euld be limited to inGlude these idontified inth Abnorm~al eatg FedUO- 4teEtetG Operating Procodr-s-apd4 ete E-A (.g., area, pr,.cess, andor effl ,.uent Frad rnntor-s, et,.)]Salem Page 2 of 5 Rev. 0 (draft E)EAL#: SS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 Site specific indications needed to monitor safety functions necessary for protection of the public must include CGontrol RFoom indications, computer generated indications and dedicated annunciation capability.

[The .pe.ifi.

should be t-1,089 us,,ed to such funct,,ns as the shut do w4 the reacto, m4aintain the core- cooled, to n~aintain the re-actor coolant system :n tact, main tamn the Spent fuel cooled-, ndto manai ontainment intac-t.]"Compensatory indications" in this context includes computer based information such as the pfees-Plant Ceomputer Ssystem and SPDS (see OP-AB.ANN-0001 (Q)). This should include all computer systems available for this use depending on specific plant design and subsequent retrofits.

Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.[Due to the limited number of safety system in operation dUiRhg cold shutdowný, re fueling and defuel-d m9..odes, no !C is iqdicated drgth eSe ModeS of operation-.]

[Due to the limited numnber- of s-afe-ty systems in eoperation dlurig cold shutdownP, r-efu clý3g and dofueed moes-, no IC is in3dica--t-ed during these modles of opera ton.][Other required Technical Speci fication shutdowns that ipve4ý' precur-sors to more ser.Gous evfents are addressedby.

rSystem M, Hazards, Or Fission Prod... .ct Ba, .DegFa .Explanation/Discussion/Definitions:

OP-AB.ANN-0001(Q) details increased monitoring and surveillance requirements as well as alternate indicators during a loss of Control Room Overhead Annunciators.

The 15 minute clock starts when the annunciators or other key control room safety function indications have been lost, or are determined to have been lost. If upon time of discovery it is determined that the annunciators or key safety function indications have been lost for at least 15 minutes prior to discovery, classification should be made under this EAL regardless of time required for restoration.

SIGNIFICANT TRANSIENTS are listed in Table S-1.The Plant Process Computer System (PPC) and Safety Parameter Display System (SPDS)serve as redundant indicators which may be utilized as compensatory measures in lieu of the Control Room Overhead Annunciators and Control Room indicators associated with safety functions.

The judgment of the Shift Manager should be used as the threshold for determining the severity of the plant conditions.

Definitions:

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: SS5.1 SGS ECG -EAL Technical Bases EP-SC-111-217 UNPLANNED:

a parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions. An UNPLANNED loss of annunciators and loss other key control room indication systems excludes scheduled maintenance and testing activities.

SIGNIFICANT TRANSIENT:

An UNPLANNED event based on EC judgment, but includes as a minimum any one of the following:

(1) automatic turbine runback greater than 25% thermal reactor power, (2) electrical load rejection greater than 25% full electrical load, (3) Reactor Trip, or (4) Safety Injection Activation.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SS6 Example EAL #1 2. SI(S2).OP-AB.ANN-0001(Q)

Loss of Overhead Annunciator System 3. UFSAR 7.7.2.10 Plant Alarm and Annunciator Systems 4. UFSAR Table 7.7-2 Overhead Annunciator Grouping Salem Page 4 of 5 Rev. 0 (draft E)EAL#: SS5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-217 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: SS5.1

SGS ECG -EAL Technical Bases EP-SC-1 11 -218 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 6 -Communications Loss of all onsite or offsite communications capabilities 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SU6.1 -UNUSUAL EVENT Loss of all Table S-2 Onsite communication methods affecting the ability to perform routine operations OR Loss of all Table S-2 Offsite communication methods affecting the ability to perform offsite notifications Table S-2 Communications Systems System Onsite Offsite Direct Inward Dial System (DID) X X Station Page System (Gaitronics)

X Station Radio System X Nuclear Emergency Telephone X System (NETS)Centrex Phone System (ESSX) X NRC (ENS) X Salem Page 1 of 4 Rev. 0 (draft E)EAL#: SU6.1 SGS ECG -EAL Technical Bases EP-SC-111-218 Basis: The purpose of this !C and its associatcd EALs is to recognize a loss of communications capability that either defeats the plant operations staff ability to perform routine tasks necessary for plant operations or the ability to communicate issues with off-site authorities.

[The lo&6 Of off Site communication a ab~iit is cXpected to be significantly more compqrehens.

than the codition essd dby 10 CFR5.72]The availability of one method of ordinary off-site communications is sufficient to inform federal, state, and local authorities of plant problems.

This EAL is intended to be used only when extraordinary means (e.g., relaying of information from non-routine radio transmissions, individuals being sent to off-site locations, etc.) are being used to make communications possible.[Site Specii, lisft foFr GP Site h8 must thc ,oss ofl 'eaS 9orao ,"9 ommuPnications (e.g., cu onmerDia telephones, sound poiorcsd phono systcma, page pa.:y sisteR (GaitronicS) and radios incalkue talkies) rmoutie usedheor opermation a.][Site apec i f (Itc) s for Off Sdte iOMnan,'catiOn l i4 ust encomopass the loss of al Mmears oa elMMUne atiser with off site authocrites.

lpS shonuld ipn fue the ENS, commercial telophono fines, telecopy torabetnssions, and dedicate d phone syýstems that are rsoutincY used far off-ite emvergency notfications.P Explanation/Discussion/Definitions:

Onsite and offsite communications include one or more of the systems listed in Table S-2.Direct Inward Dial System (DID)Direct Inward Dial (DID) system is named for the dominant feature of the commercial telephone service provided by the local telephone company for the site. DID allows station telephones to be extensions or tied lines of the same systems. These exchanges can take advantage of backup power supplies provided to the stations, and may use either PSEG microwave, commercial telephone system microwave, or buried cable transmission systems to maintain external communications.

This commercial telephone service is available as an additional backup for the NETS and GentrexIESSX 1 system.Station Page System (Gaitronics)

Gaitronics is a completely transistorized voice communication system with five voice channels: one page and five party. The system is designed for use in extreme environmental conditions such as dust, moisture, heat and noise. The system consists of handsets, speakers and their associated amplifiers.

The power for this system is 120 volts AC from an inverted DC source to provide reliable communications during an emergency.

Salem Page 2 of 4 Rev. 0 (draft E)EAL#: SU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-218 Station Radio System The Operations and Fire Protection Department UHF radio system is a multi-frequency system used routinely by both station Operations Departments and the Fire Protection Department.

When an emergency event is declared, these radio frequencies serve both station Operations Support Centers (OSC).Nuclear Emergency Telephone System (NETS)The Nuclear Emergency Telecommunications System (NETS) is a privately controlled, self-contained telephone exchange that operates as a closed system, not accessible from other phone exchanges.

This feature allows the system to be dedicated to emergency response use. The system may use PSEG microwave, commercial telephone system microwave, fiber optics, or buried cable transmission as needed. The exchange switching equipment is maintained at the Environmental

& Energy Resource Center (EERC). As an independent system with an uninterruptible power supply, it may operate with or without local phone service or external power.Centrex Phone System (ESSX)The Centrex/Electronic Switch System Exchange 1 (CentrexiESSX

1) is also a privately controlled exchange, which PSEG operates with its own microwave signal system. This system is also independent of local phone service, since each circuit is independently wired.The microwave signal is generated from corporate facilities in Newark, NJ, separated from any local effects of weather or telephone use. The exchange is accessible from other exchanges, but circuits are located only in PSEG facilities.

It is considered the primary backup for the NETS system.NRC (ENS)The Emergency Notification System (ENS) is a dedicated communications system with the NRC, which is part of the Federal Telecommunications System (FTS) and consists of direct lines to the NRC. FTS lines are used to provide general accident information.

These telephones are installed in the Control Room, TSC, and the EOF.This EAL is the hot condition equivalent of the cold condition EAL CU5.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SU6 Example EAL #1, #2 2. PSEG Nuclear Emergency Plan, Section 7 3. UFSAR 9.5.2 Communications System Salem Page 3 of 4 Rev. 0 (draft E)EAL#: SU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-218 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: SU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-219 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: S -System Malfunction 7 -Fuel Clad Degradation Fuel clad degradation 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SU7.1 -UNUSUAL EVENT VALID Letdown Line Monitor readings indicating fuel clad degradation greater than EITHER of the following Technical Specification allowable limits: " 1R31Ainwarning

2R31 in alarm Basis: This EAL is included because it is a precursor of more serious conditions and, as result, is considered to be a potential degradation of the level of safety of the plant.Escalation of this EAL to the ALERT level is via the Fission Product Barriers.EALH1 This threshold addresses letdownSite-speifi-e radiation monitor readings that provide indication of a degradation of fuel clad integrity.

rct, -01A10 -;, IDIA10 -F-;I-,4 A-1 -1 4L-- I_ 11~a II1/4~ ii tot I I v.~i I tot Lv., to tot I I! I fLAt ii totS Liv.'! Ito Itototo-1ItSXJUX,-VV~71~7VflJQ7CL~J..Y-t'pc~ 11- .il --i 1 h irc'1 Z, *1 I tI ý P -!i t~~'f 1 1- -~ I -I, I~ -týp .1 -iti 4 r tA iripIr r I~P-1 CWTT TTT1ZWt;ATFkZY WT me. ririnO ne.rtii/system~~~

PGirnc~ad radioS,'A Waeki ta-944s98, cUt/n 4'y usdfr p-1 in.r _ I" 1 I= 1"£' "1 _L i i 'rInntt~ r,c C. i, r -n e. Crrt ý--rnrrvt" 1 1n t~nr'~rrx C' fin C' CPI Ii iCtPr i ^ r-i'iý Cc' ttIn t~C'Ct,-n ntI ryn n ' n 0 Lx~rttrx ,lsoti io,tttio oi o v o t... .... .. .It .... ..... lto~.... t .... .. to .........

.... .......t oo L t vtt o v.,i U iit o,,oP t/nati S With off 6sit authortics.

ThS shOuld :nC-udc ehc E-NS r teeph onc lies eleoytrnsisins nddeiatd hnesytmstt -e routincly used for- oifs/t kmera enc optrfiaP5'ti

__ofeints._Q1--Y_

Explanation/Discussion/Definitions:

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: SU7.1 SGS ECG -EAL Technical Bases EP-SC-1 11-219 Letdown Line Monitors serve as a failed fuel detector by monitoring gamma levels in the reactor coolant letdown line. Unit 1 Letdown Line Monitor (1 R31A) is a gross iodine monitor.The Unit 2 Letdown Line Monitor (2R31) is an ion chamber which measures letdown line activity.

The Letdown Line Monitor "warning" setpoints are administratively set at 50% of the"alarm" setpoints.

1R31A "alarm" setpoint is based on 1% failed fuel. The "warning" setpoint represents about 0.5% failed fuel and has been selected because the setpoint would be readily identifiable on Control Room instrumentation.

2R31 "alarm" setpoint is based on 0.1% failed fuel. This setpoint is readily identifiable and also representative of typical values of coolant activity at Technical Specification limits.Read-outs for these monitors can be obtained in the Control Room.Other radiation monitors that may be used to confirm a valid Letdown Line Monitor alarm include:* 1(2)R4 Charging Pump Room* 1(2)R26 Reactor Coolant Filter* Containment Area Rad Monitors (1 (2)R2, 1(2)7, 1(2)1 0A, 1(2)1 OB)Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SU4 Example EAL #1 2. PSBP 315733 Radiation Monitoring System Manual, Unit 1 3. PSBP 315734 Radiation Monitoring System Control Manual, Unit 2 4. UFSAR 9.3.5.3 Safety Evaluation (Failed fuel Detection System)5. UFSAR 11.4 Radiological Monitoring

6. Sl(S2).OP-AB.RC-0002 (Q) High Activity in the Reactor Coolant System Salem Page 2 of 2 Rev. 0 (draft E)EAL#: SU7.1 SGS ECG -EAL Technical Bases EP-SC-1 11 -219 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: S -System Malfunction 7 -Fuel Clad Degradation Fuel clad degradation 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown SU7.2 -UNUSUAL EVENT EAL: Basis: This EAL is included because it is a precursor of more serious conditions and, as result, is considered to be a potential degradation of the level of safety of the plant.Escalation of this EAL to the ALERT level is via the Fission Product Barriers.EAl #2 This threshold addresses coolant samples exceeding coolant technical specifications for transient iodine spiking limits (Technical Specification Figure 3.4-1).[Sur h as B iWR elecj monitors, PWR f-ailed--fuel m ; onitors, etc.][Sito Sperific list for commn'ica4,'on108, must enompR4ass thc loss of all meanS of comm3unication (e.g., comrc. teepons 4-91913Sond powered phon~e systems6, page pa-4y system" "Gadio", s' / .... r.uti.. y used for opora qt.....][Site specif f~ist for, Gf itcOMMUniations loss must enco mpass the loss of all moans ot comm.unic;ations with off site author. t"es. Thý S hould the , ,mrctpho-e lnes, t-..,opy tranmissonso,.-

d dedicated phone systems that are ,out..,n, used for offsite emergnc notif- tionaU -8.]1 Explanation/Discussion/Definitions:

An Unusual Event is only warranted when actual fuel clad damage is the cause of the elevated coolant sample (as determined by RCS sample analysis confirmation).

Escalation to an ALERT or higher emergency classification occurs if a sample analysis of reactor coolant activity exceeds 300 pCi/gm DEl-1 31 via EAL FB4-L.Salem Page 1 of 3 Rev. 0 (draft E)EAL#: SU7.2 SGS ECG -EAL Technical Bases EP-SC-1 11-219 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SU4Example EAL #2 2. SGS Technical Specification Section 3.4.8 -Unit 1 Specific Activity 3. SGS Technical Specification Section 3.4.9 -Unit 2 Specific Activity 4. SI(S2).OP-AB.RC-0002(Q)

High Activity in Reactor Coolant System Salem Page 2 of 3 Rev. 0 (draft E)EAL#: SU7.2 SGS ECG -EAL Technical Bases EP-SC-1 11 -219 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: SU7.2 SGS ECG -EAL Technical Bases EP-SC-111-220 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

S -System Malfunction 8 -RCS Leakage RCS Leakage 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown EAL# & Classification Level: SU8.1 -UNUSUAL EVENT EAL: UNIDENTIFIED LEAKAGE or PRESSURE BOUNDARY LEAKAGE > 10 gpm (Note 6)OR IDENTIFIED LEAKAGE > 25 gpm (Note 6)Note 6: See the Fission Product Barrier Table for possible escalation above the UNUSUAL EVENT due to RCS Leakage Basis: This 4f-,-EAL is included as a NQUE because it may be a precursor of more serious conditions and, as result, is considered to be a potential degradation of the level of safety of the plant.The 10 gpm value for the UNIDENTIFIED or PRESSURE BOUNDARY LEAKAGE was selected as it is observable with normal Ceontrol Rroom indications.

Lesser values must generally be determined through time-consuming surveillance tests (e.g., mass balances).

Relief valve normal operation should be excluded from this IGEAL. However, a relief valve that operates and fails to close per design should be considered applicable to this IG-EAL if the relief valve cannot be isolated.The EAL for identified leakage is set at a higher value due to the lesser significance of IDENTIFIED LEAKAGE in comparison to UNIDENTIFIED or PRESSURE BOUNDARY LEAKAGE. In either case, escalation of this IW-EAL to the ALERT level is via Fission Product Barrier Degradation ,GsEALs.__ 01AIM -;- -;--4-- MIAIM r-l-'4--i L- --I --II. 1. V I i I. ".I L'J-- -' L I* I I~V I"t*.) L1, a vIIt4 W" i L'S.)ifitif ffifiiiiifi-j. .-a[Site specific fist fer- on Site cOMmun4icatiGon

/0, lesMUst -ncopassth, lo9 10Sef al 8mneans a r'rmI fr ' =jz~~c 40 ay t-- ___ In~~ArIrIIlrIrrr

,cfr~'..1 WI 1 11 1 1-1 1 I _j 4 14CýPM 4 M 9 r- f F4 Pq!A/ PQ _Af.AQ.4 W P._ --.I-.-.....Salem-z-I-/vr.. v.vl Page 1 of 4 Rev. 0 (draft E)EAL#: SU8.1 SGS ECG -EAL Technical Bases EP-SC-111-220

[Site &pecifi list for Off Site G9P4,iati91n I. ,os mRust encomp4a8 the Joes of all means atf com3munication With off site authoritges.

ThýS ShOUld inclu4de the ENS, coemmercial telc phon-e line&, telecOPY tr-ansmissions9P, and dedicated phone systems that are roeutinely used Afo ofst Explanation/Discussion/Definitions:

RCS Leakage is defined as any leakage of Reactor Coolant this is unisolable or affects Pressurizer level. RCS Leakage of the magnitude described in this EAL is consistent with an Unusual Event classification and should be declared immediately.

The Technical Specification definitions for UNIDENTIFIED LEAKAGE, IDENTIFIED LEAKAGE and PRESSURE BOUNDARY LEAKAGE are provided below.Relief valve normal operation (e.g., PZR PORV or safety valves) should be excluded from emergency classification under this EAL. A relief valve that fails to close per design and cannot be isolated from the Control Room, however, should be considered applicable to this EAL.Utilizing the leak before break concept, it is anticipated that there will be indications of minor RCS boundary leakage prior to a fault escalating to a major leak or rupture. Detection of low levels of leakage while pressurized permits monitoring for catastrophic failure or rupture precursors.

The Control Room staff is equipped with the Plant Computer (PRIM SYS LEAK RATE program) and manual methods of determining the extent of RCS leakage.Examples of RCS leakaqe and applicability include: Example #1: A rapidly lowering Volume Control Tank (VCT) level is identified during a Radwaste evolution involving the draining of the #12 Mixed Bed Demineralizer (MBD). The Control Room staff identifies the condition and the drain valve on the MBD is closed. Charging flow has not changed and VCT level is stabilized within 3 minutes. The calculated leak rate is 73 gpm for 3 minutes.This is not reportable because the leakage did not affect pressurizer level and the leak was isolable from the RCS. Note that Tech Spec limits still apply.Example #2: A Unit 2 RCS leakrate calculation identified a 30-gpm leak. VCT level has started to drop unexpectedly and enough time has passed that there are minor variations in pressurizer level. The source of the leak is unknown. After about 20 minutes, it was determined that the source of the leak was the stem leakoff line from the 2CV55.This event should be classified within the 15 minute clock and declared an Unusual Event even though the leak could have been isolated.

Any reduction in pressurizer level, which can be attributed to a Reactor Coolant System leak should be quantified and the Technical Specification entered and the applicable EAL entered as appropriate.

Salem Page 2 of 4 Rev. 0 (draft E)EAL#: SU8.1 SGS ECG -EAL Technical Bases EP-SC-1 11-220 The use of increasing charging flow to quantify Reactor Coolant System leakage is acceptable provided there is an actual Reactor Coolant System leak. This could result in a stable pressurizer level and should be reviewed against Technical Specifications and the ECG as applicable.

If at any time the source of the leakage is unknown and it meets the ECG criteria, the Emergency Coordinator should classify the event.Escalation to the ALERT emergency classification level is via EALs in Category F. Note 6 has been added to remind the EAL-user to review the Fission Product Barrier EALs for possible escalation to higher emergency classifications.

Definitions:

UNIDENTIFIED LEAKAGE: As defined in T/S, shall be all leakage which is not IDENTIFIED LEAKAGE.PRESSURE BOUNDARY LEAKAGE: As defined in T/S, shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.IDENTIFIED LEAKAGE: As defined in T/S, shall be leakage (except Reactor Coolant Pump Seal Water Injection) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or, shall be leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or, shall be Reactor coolant system leakage through a steam generator to the secondary system (primary-to-secondary leakage).EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SU4 Example EAL #2 2. Technical Specifications, Definitions

3. Technical Specifications 3.4.6.2 -Unit 1 Operational Leakage 4. Technical Specifications 3.4.7.2 -Unit 2 Operational Leakage 5. UFSAR 5.2.7.2 Indication in Control Room 6. S1(S2).OP-AB.RC-0001(Q)

Reactor Coolant System Leak 7. SI(S2).OP-SO.RC-0004(Q)

Identifying and Measuring Leakage 8. SC.RA-AP.ZZ-0051 Leakage Monitoring and Reduction Program 9. SI(S2).OP-ST.RC-0008(Q)

Reactor Coolant System Water Inventory Balance Salem Page 3 of 4 Rev. 0 (draft E)EAL#: SU8.1 SGS ECG -EAL Technical Bases EP-SC-1 11-220 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: SU8.1 EALs for: Fission Product Barriers SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation CFSTs Potential Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB1-P (4 points)EAL: CFST Core Cooling PURPLE path exists Basis:[These th ÷Ieodaar f.. Dr PWK4s "°g G'tik.l S '-',Y, FU...' ý,Status Tr,,ee (CSFST)m....or..g and fun.tina, ,Fe, St .... pr.ocedures.

For more information, please refer to Sr>onfinq 2 oq~f thc: rip, lcti 0-+-+-lI -- T,-k-I-1,-fA A Core Cooling -ORANE-PURPLE indicates subcooling has been lost and that some clad damage may occur.Heat Sink -RED When heat sik-4-s--equred

-,,4Ga.a4 he-ul-t h tt under extrem11.e-cha11eng)c-.

Explanation/Discussion/Definitions:

CFST status will not be used for event classification until the Control Room staff has implemented the CFSTs. The Core Cooling CFST is illustrated in Attachment 2, page 4.Adverse Containment setpoints appear in the Heat Sink CFST. Adverse Containment conditions exist if Containment pressure exceeds 4 psig or R44 Containment radiation dose rates exceed 1 E05 R/hr or R44 dose exceeds 1 E06 R.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Potential Loss 1.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree 3. NC.EP-EP.ZZ-0201 (Q) TSC -Integrated Engineering Response Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB1-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FB1 -P SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation CFSTs Potential Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB2-P (4 points)EAL: Basis: Heat Sink RED when heat sink is required indicates the ultimate heat sink function is under extreme challenge.

Explanation/Discussion/Definitions:

CFST Heat Sink RED Path entry conditions affects both the Fuel Clad and RCS Barriers.Therefore, minimum classification would be SAE.A barrier loss classification should not be made if the Heat Sink RED Path is the result of procedurally required Auxiliary Feedwater Flow control.CFST status will not be used for event classification until the Control Room staff has implemented the CFSTs. The Heat Sink CFST is illustrated in Attachment 2, page 6. Adverse Containment setpoints appear in the Heat Sink CFST. Adverse Containment conditions exist if Containment pressure exceeds 4 psig or R44 Containment radiation dose rates exceed 1 E05 R/hr or R44 dose exceeds 1 E06 R.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Potential Loss 1.B 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.03 Heat Sink Status Tree 3. 1(2)-EOP-FRHS-1 Response to Loss of Secondary Heat Sink 4. NC.EP-EP.ZZ-0201 (Q) TSC -Integrated Engineering Response Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB2-P SGS ECG -EAL Technical Bases EP-SC-I 11-221 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FB2-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Core Exit TCs Potential Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB3-P (4 points)EAL: 5 or more CETs > 700°F Basis:[Core Exit ThermGcouple Rcadings aro ipnluded in addition to th e Cntcal Safet F-unctionS to inclu4de conditions whcn the CSF-s may not be in use (ntatnafrSIis bieoc4od or GptS Which do not a.. a CS.... s.h....Loss Threshold A The site specific 'e- ...d.... should correspond to significant superheating of the coolnt.[Th is vý4e ,,,t.pially .r...p..d.

to the tP p ...r... r'eadi'g that '-' ...te .c .,vcoolin RED )in Fue-Clad -BarrieFiss threshold

!.A thich is usua..y about 1200 degrees F-.]Potential Loss Threshold A The site specific reading should correspnd tofive core exit thermocouple (CET) temperatures

> 700°F indicates a loss of subcooling.

[___ This va"'e furpir'aIg G~~6Gd to the ~ t ptr~ r 'r-ý that indlicates cor-e coolinq ORANGE in F'uel Clad Barrier potetial loss reo sh÷od 1,A is USUallY about 700 to 900 deofees Al Explanation/Discussion/Definitions:

Core exit thermocouple (CET) readings greater than 700°F signal a CFST Core Cooling PURPLE path condition.

CET readings are used as a fission product barrier threshold in addition to the CFST thresholds to address events in which the CFSTs may not yet be in use.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Potential Loss 3.A Salem Page 1 of 3 Rev. 0 (draft E)EAL#: FB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree Salem Page 2 of 3 Rev. 0 (draft E)EAL#: FB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: FB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: EAL: F -Fission Product Barrier Degradation Inventory Potential Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB4-P (4 points)RVLIS < Table F-I thresholds Table F-1 RVLIS Thresholds RVLIS RCPs Full Range 39% None 44% 4 30% 3 Dynamic Range 20% 2 13% 1 Basis: There is no Loss threshold associated with this item.The values for the Potential Loss thresholds corresponds to approximately the top of the active fuel.rr7-. ,-c-r-c--r-tt-- i; .41- t----tfutOf v uw ig D f eý, ftft f ututt ; i Lut u! I;~ tv ~ , z fu; tu LH &Y ii-QFA.NGEZ A;th~ Thcp .4in nnifn '1hi in thi.P thrizhrild lhpf fd hn op ~ nfwihfnCF Ma4ueA 1ý ýExplanation/Discussion/Definitions:

The specified RVLIS readings (Table F-1) and the associated number of running RCP pumps are used in the CFSTs to signal core uncovery and are, therefore, indication of inadequate Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB4-P SGS ECG -EAL Technical Bases EP-SC-11 11-221 coolant inventory.

If the RVLIS thresholds are exceeded, a core covered condition cannot be confirmed.

According to the CFST Core Cooling PURPLE path, this water level indicates subcooling has been lost and that some fuel clad damage may occur. RVLIS readings are used as a fission product barrier threshold in addition to the CFST thresholds to address events in which the CFSTs may not yet be in use.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Potential Loss 4.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FB4-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation EC Judgment Potential Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB5-P (4 points)EAL: ANY condition in the opinion of the Emergency Coordinator that indicates potential loss of the Fuel Clad barrier Basis: Thisese thresholds addresses any other factors that are to be used by the ErnergeRy Di-ecte-Emergency Coordinator in determining whether the Fuel Clad barrier is lest G potentially lost. In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in Em.rgcncY ,Directo.

Emergency Coordinator judgment that the barrier may be considered l9st-Or-potentially lost.Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the Fuel Clad barrier is potentially lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences." Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance.

Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results." Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of AC power (Station Blackout) and ATWT EALs to assure timely emergency classification declarations.

Salem Page 1 of 2 Rev. 3(draft E)EAL#: FB5-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Potential Loss 8.A Salem Page 2 of 2 Rev. 3(draft E)EAL#: FB5-P SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation CFSTs Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB1-L (5 points)EAL: CFST Core Cooling RED path exists Basis:[The.se 4 d are fo, P,/4R using ,,-,;-l ,fe_, F .unction Status. Tr-F (CSF,-ST MOnioP n -nd -fncton res~toration proedures.

Foer more information., please ýrefert Secto 32.9- of th i docudn-ment.]

Loss Th re held-A Core Cooling- RED indicates significant superheating and core uncovery and is considered to indicate loss of the Fuel Clad Barrier.Explanation/Discussion/Definitions:

CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs. The Core Cooling CFST is illustrated in Attachment 2, page 4.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Loss 1.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB 1 -L SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FBI-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Core Exit TCs Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB2-L (5 points)EAL: 5 or more CETs > 1200°F Basis:[These thr;esholds are for PWRs using CGritial Safty Status ..r,, (CSF.T)monitoring and fnctfional1 r-esto~ration pro~edfures.

ForF moro infrmaion plaerfer to9 Soction 3.9 of this document.]

Pnfcnimpip I ncz. Thrp-hplcl A[Core Exit T-hermocoUPle ReadingS are included in additio to the Qr~t~a1,Safet Functons o inlude conditios when the CSF-s may, not bein use (initiation after- S! is blcked)or- plants which do not have a CSF= &cheme.]Loss Threshold A The five core exit thermocouple (CET) temperatures

> 1200°F indicates site speifi, reading should correspond to significant superheating of the coolant.[This value typiC-aly corrFesponds to the temper ature reading that i~di~ate coro c-ooling-ED in Fue" Clad Bar ei" threshold

!.A which is usually about 1200 dgrees F-.]Explanation/Discussion/Definitions:

Core exit thermocouple (CET) readings greater than 1,200°F signal a CFST Core Cooling RED path condition.

CET readings are used as a fission product barrier threshold in addition to the CFST thresholds to address events in which the CFSTs may not yet be in use.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Loss 3.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree Salem Page 1 of 3 Rev. 0 (draft E)EAL#: FB2-L SGS ECG -EAL Technical Bases EP-SC-I 11-221 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: FB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: FB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Radiation Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB3-L (5 points)EAL: Containment radiation monitor R44A or R44B reading > 300 RPhr Basis: The site specific reading is a value which indicates the release of reactor coolant, with elevated activity indicative of fuel damage, into the containment.

[T~he-reaedig-sheuld-be-~euleate4-suin-h-e-setant-neou e~ease-an-ee thc reactor coolant noble gas- and iod~ne 43n -Fnly aSSocia-ted with a cc~~taG G f 300#QCigrn dose equivient 11431 into the conptainm~ent atmosphere.]

Reactor coolant concentrations of this magnitude are several times larger than the maximum concentrations (including iodine spiking) allowed within technical specifications and are therefore indicative of fuel damage.This value is higher than that specified for RCS barrier Loss thresheld A#RB1-L. Thus, this threshold indicates a loss of both the Fuel Clad barrier and RCS barrier that appropriately escalates the emergency classification level to a Site Area Emergency.

-4ca-ut~~~icn:N itiFmatt ecognize that in the event the rdato nntr: estv to shine from theI rat'or yý&e c rppig pnu readig- !b present and anthe There is no Potential Loss threshold associated with this item.Explanation/Discussion/Definitions:

1(2)R44A and 1(2)R44B are the Containment High Range area radiation monitors.

The threshold value of 300 R/hr has been calculated assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with a concentration of 300 pCi/gm Dose Equivalent 1-131 into the Containment atmosphere.

300 pCi/gm Dose Equivalent Iodine-1 31 (DEl-1 31) corresponds to approximately 2.8% fuel clad damage.Salem Page 1 of 3 Rev. 0 (draft E)EAL#: FB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Loss 6.A 2. Calculation by Nuclear Fuels Group file title DS1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 02/10/95 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: FB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: FB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Other Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB4-L (5 points)EAL: Coolant activity > 300 pCilgm dose equivalent 1-131 Basis: The site specific value eerresPOne is te-300 ýCi/gm dose equivalent 1-131 Assessment by the NEI EAL Task Force indicates that this amount of coolant activity is well above that expected for iodine spikes and correspRodS to less than 5% fu,,! clad damag .This amount of radioactivity indicates significant clad damage and thus the Fuel Clad Barrier is considered lost.[TheVaý8GaP e exressd ether in m94hr obs, e~v don the sample~ 9r as 44zgn4 r-esult-s from analysi.j There is no Potential Loss threshold associated with this item.Explanation/Discussion/Definitions:

The threshold value of 300 pCi/gm Dose Equivalent Iodine-131 (DEl-131) is based upon an engineering calculation and corresponds to approximately 2.8% fuel clad damage.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Loss 2.A 2. Calculation by Nuclear Fuels Group file title DS1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 2/10/95 3. SI(S2).OP-AB.RC-0002 (Q) High Activity in Reactor Coolant System Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation EC Judgment Loss of Fuel Clad 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown FB5-L (5 points)EAL: Basis: These-This thresholds addresses any other factors that are to be used by the E=mergenGy Coordinator in determining whether the Fuel Clad barrier is lost--e peten.ially In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in Er ..rgenc Directo.Emerqency Coordinator judgment that the barrier may be considered lost or potentially le ..Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the Fuel Clad barrier is lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences.

Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance." Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results.* Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of AC power (Station Blackout) and ATVVT EALs to assure timely emergency classification declarations.

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: FB5-L SGS ECG -EAL Technical Bases EP-SC-1 11-221 Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Fuel Clad Loss 8.A Salem Page 2 of 2 Rev. 0 (draft E)EAL#: FB5-L SGS ECG -EAL Technical Bases EP-SC-111-222 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Isolation Potential Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB1-P (4 points)EAL: CFST Thermal Shock RED path exists Basis:[These thresholds are for Pt44R usifg, Critical Safety F=Untion Status Tree (QSF=ST)monitorig and functional restoration P-rocedur-es.

Fr- moro information, refer- to Section3.

o--1:-1 1-r--L --IAJ A A T i i I I ..............RCS Tteg4iy-Thermal Shock -RED indicates an extreme challenge to the safety function derived from appropriate instrument readings.rn --4:-1 1~-~L~I,-J D I I t:~-;I It Heat Sink D h h 4eq"-Ue nc ' ite-heat-si Ie-n-s under extreme challenge-.

There is no Loss threshold associated with this item.Explanation/Discussion/Definitions:

CFST status will not be used for event classification until the Control Room staff has implemented the CFSTs. The Thermal Shock CFST is illustrated in Attachment 2, pages 7 and 8. The Heat Sink CFST is illustrated in Attachment 2, page 6. Adverse Containment setpoints appear in the Heat Sink CFST. Adverse Containment conditions exist if Containment pressure exceeds 4 psig or R44 Containment radiation dose rates exceed 1 E05 R/hr or R44 dose exceeds 1 E06 R.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Potential Loss 1.A Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RBI-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.04 Thermal Shock Status Tree 3. NC.EP-EP.ZZ-0201 (Q) TSC -Integrated Engineering Response Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RB1-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RB1-P SGS ECG -EAL Technical Bases EP-SC-111-222 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Isolation Potential Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB2-P (4 points)EAL: Basis: Heat Sink RED when heat sink is required indicates the ultimate heat sink function is under extreme challenge.

There is no Loss threshold associated with this item.Explanation/Discussion/Definitions:

CFST Heat Sink RED Path entry conditions affects both the Fuel Clad and RCS Barriers.Therefore, minimum classification would be SAE.A barrier loss classification should not be made if the Heat Sink RED Path is the result of procedurally required Auxiliary Feedwater Flow control.CFST status will not be used for event classification until the Control Room staff has implemented the CFSTs. The Thermal Shock CFST is illustrated in Attachment 2, pages 7 and 8. The Heat Sink CFST is illustrated in Attachment 2, page 6. Adverse Containment setpoints appear in the Heat Sink CFST. Adverse Containment conditions exist if Containment pressure exceeds 4 psig or R44 Containment radiation dose rates exceed 1 E05 R/hr or R44 dose exceeds 1 E06 R.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB2-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Potential Loss 1..B 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.03 Heat Sink Status Tree 3. 1(2)-EOP-FRHS-1 Response to Loss of Secondary Heat Sink 4. NC.EP-EP.ZZ-0201 (Q) TSC -Integrated Engineering Response Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB2-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category: Subcategory:

F -Fission Product Barrier Degradation Inventory Initiating Condition:

Mode Applicability:

EAL# & Point Value: Potential Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB3-P (4 points)EAL: Basis: Potential Lss Threshold A This threshold is based on the apparent inability to maintain normal liquid inventory within the Reactor Coolant System (RCS) by normal operation of the Chemical and Volume Control System which is considered to be the flow rate equivalent to one charging pump discharging to the charging header. Minimizing isolating letdown is a standard abnormal operating procedure action and may prevent unnecessary classifications when a non-RCS leakage path such as a CVCS leak exists. The intent of this condition is met if the leak is in Letdown and attempts to isolate Letdown are NOT successful.

Additional charging pumps being required is indicative of a substantial RCS leak.[For plants with low capacity charging PUMPS, a 50 gpM indicated leak rate value may be U,,ed tO indiate the Potential Less.]Explanation/Discussion/Definitions:

Significant leakage from the RCS requires implementation of S1 (S2).OP-AB.RC-0001(Q).

Actions required by this procedure specify the use of one Centrifugal Charging Pump, discharging to the charging header, and Letdown reduced to a minimum. If RCS leakage results in an inability to maintain the specified Pressurizer (PZR) level with a normal charging lineup and minimum Letdown flow using one Centrifugal Charging Pump, an RCS inventory loss is occurring that would require initiation of Reactor Trip and Safety Injection (SI) and entry into EOP-TRIP-1.

This RCS Potential Loss assumes that any event that would result in significant RCS mass loss will require at least an Alert emergency classification.

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 Non-RCS leakage events (such as steam or feedwater system breaks) in which no mass is lost from the RCS should not be classified under this RCS barrier Loss. SGTRs that result in entry into 1(2)-EOP-SGTR-1 shall be classified under RCS Barrier Loss RB3-L. If a SGTR does not result in I(2)-EOP-SGTR-1 entry, it should be classified as a minimum under this RCS barrier Potential Loss if PZR level cannot be maintained above 17%.When PZR level drops to 17%, Letdown isolates and pressurizer heaters deenergize.

This condition is signaled by overhead annunciator E-36, PZR HTR OFF LVL LO. Pressurizer level is indicated on LI-459A, LI-460A, LI-461, associated computer points and SPDS.The design flowrate of one centrifugal charging pump is 150 gpm.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Potential Loss 2.A 2. SI (S2).OP-AB.RC-0001 (Q) Reactor Coolant System Leak 3. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 4. 1(2)-EOP-SGTR-1 Steam Generator Tube Rupture 5. S1(S2).OP-AR.ZZ-0005(Q)

OHA E-36, PZR HTR OFF LVL LO 6. Sl(S2).OP-SO.CVC-0002(Q)

Charging Pump Operation Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation EC Judgment Potential Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB4-P (4 points)EAL: ANY condition in the opinion of the Emergency Coordinator that indicates potential loss of the RCS barrier Basis: Thisese thresholds addresses any other factors that are to be used by the Emergency Coordinator in determining whether the RCS barrier is lest o potentially lost. In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in Emcrgency Directo.Emergency Coordinator judgment that the barrier may be considered le-st or-potentially lost.Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the RCS barrier is potentially lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences." Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance.

Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results.* Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of AC power (Station Blackout) and ATWT EALs to assure timely emergency classification declarations.

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB4-P SGS ECG -EAL Technical Bases EP-SC-1 11 -222 Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Potential Loss 8.A Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB4-P SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category: Subcategory:

F -Fission Product Barrier Degradation Radiation Initiating Condition:

Mode Applicability:

EAL# & Point Value: EAL: Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB1-L (5 points)ANY of the following Containment radiation monitor readings: " 1(2)R2 > 1000 mR/hr* 1(2)R44A > 10 R/hr" 1(2)R44B > 10 R/hr Basis: The site speGifi--reading-4ss are a-values which indicates the release of reactor coolant to the containment.

In rn r -n 11t~n In I i n ýIn/I to t -n Ca oli 1r"rn Inr I i !P 1 C. JTIQat11 r nn~t nn.'~ ron In LDDLADLALAf~r nn /n Df e LALN A no nA q DlALALALA tnj~r=Qjnn r-:WVI-r1C11 41-w l b'Ut),;1 -;,, l ; tf/ .*,' ;L ;; wf /,i,) 17ay 1;;1 11iU ;;;;-1; ,.1 ;;,1;;;I I J Theis readings will be less than that specified for Fuel Clad barrier threshold 6FB3-L. Thus, this threshold would be indicative of a RCS leak only. If the radiation monitor reading increased to that specified by Fuel Clad barrier threshold, fuel damage would also be indicated.

[Ho~evor-, if thc &ito ape cific ph~ySical location of the containment Fadiatin mn4Gitor niii-q, f~n rn4io,*~nn Arnrnm n ,.r-o,-,4 ff rn~Ipnqrr4 QC'Q po' 1-n ' vi ,I1I ppf lip dL,2in ujhpdr Lrnmr......................

~-.---.--------

4f fthi.c thro~chnid 4 chntjd ho, n_#..fr _ nhfhr .'iftq iRdi,.Gat.fiens of RCG /eak&14bstit~t9G There is no Potential Loss threshold associated with this item.Explanation/Discussion/Definitions:

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB1-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 130' Containment Area Rad Monitor 1(2)R2 has an instrument scale range of 0.1 mR/hr to 10 R/hr and, therefore, offers the preferred method of assessing this RCS Barrier Loss. 1 R/hr on this monitor is indicative of the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with Technical Specification concentrations into the Containment atmosphere.

These readings are less than that specified for Fuel Clad Barrier Loss FB3-L since this EAL attempts to identify RCS leakage assuming RCS activity is at the Technical Specification limit.Classification under this EAL should not be made based upon crud burst evolutions or other non-RCS leakage events.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Loss 6.A 2. Calculation by Nuclear Fuels Group file title DS1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 2/10/95 Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB 1-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category:

F -Fission Product Barrier Degradation Subcategory:

Inventory Initiating Condition:

Loss of RCS Mode Applicability:

1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown EAL# & Point Value: RB2-L (5 points)EAL: Subcooling

< 0°F (as a result of RCS leakage)Basis: Loss Threshold A This threshold addresses conditions where leakage from the RCS is greater than available inventory control capacity such that a loss of subcooling has occurred.

The loss of subcooling is the fundamental indication that the inventory control systems are inadequate in maintaining RCS pressure and inventory against the mass loss through the leak.Explanation/Discussion/Definitions:

RCS subcooling of 0°F or less is a criterion in the CFST Core Cooling YELLOW path (or higher) and is monitored in the Continuous Action Summary (CAS). Subcooling is indicated in the Control Room on Subcooling Margin Monitor Channel A and Channel B. This threshold focuses on RCS inventory loss due to LOCA conditions.

Non-RCS leakage events (such as steam or feedwater system breaks) in which no mass is lost from the RCS should not be classified under this RCS barrier Loss. Subcooling equal to or less than 0°F is indication that leakage from the RCS barrier is greater than the available inventory control capacity.This threshold does not apply to primary-to-secondary leakage events since adequate injection capability should be available for the spectrum of such events including Steam Generator Tube Rupture (SGTR). Refer to RCS barrier Loss RB3-L for SGTR.EOP directed actions resulting in deliberate subcooling reduction (e.g. during SGTR saturated recovery), steam/feedwater line breaks, or momentary reductions below 0°F that are recoverable (e.g. SI flow reduction sequence) should not be classified under this EAL.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Loss 2.A Salem Page 1 of 3 Rev. 0 (draft E)EAL#: RB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree Salem Page 2 of 3 Rev. 0 (draft E)EAL#: RB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: RB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB3-L (5 points)EAL: SGTR requiring ECCS (SI) Actuation Basis: This threshold addresses the full spectrum of Steam Generator (SG) tube rupture events in conjunction with Containment barrier Loss thresholds.

It addresses RUPTURED SG(s) for which the leakage is large enough to cause actuation of ECCS (SI). This is consistent to the RCS leak rate barrier Potential Loss threshold.

[F-eF plants that havol implemented Wcstingheuse Owpor-s Group emeorgency nespose guides, this ,-epIet,, is deos.,rIbd b,, into, E=-3 .....i~e by °By itself, this threshold will result in the declaration of an Alert. However, if the SG is also FAULTED (i.e., two barriers failed), the declaration escalates to a Site Area Emergency per Containment barrier Loss thresholds.

There is no Potential Loss threshold associated with this item.Explanation/Discussion/Definitions:

This EAL is indicative of a loss of RCS inventory due to a Steam Generator Tube Rupture (SGTR) in which the leakage is large enough to cause actuation of Safety Injection (SI).EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Barrier Loss 4.A 2. 1(2)-EOP-SGTR-1 Steam Generator Tube Rupture 3. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation EC Judgment Loss of RCS 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown RB4-L (5 points)EAL: Basis: Thisese thresholds addresses any other factors that are to be used by the DieetG-rEmerqency Coordinator in determining whether the RCS barrier is lost t'-pe-ti-fly Iost. In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in EMcrgccy .Direct.rEmergency Coordinator judgment that the barrier may be considered lost r peotentially lest.Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the RCS barrier is lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences.

Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance.

Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results." Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of AC power (Station Blackout) and ATWT EALs to assure timely emergency classification declarations.

Salem Page 1 of 2 Rev. 0 (draft E)EAL#: RB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-222 Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 RCS Loss 8.A Salem Page 2 of 2 Rev. 0 (draft E)EAL#: RB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation CFSTs Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB1-P (2 points)EAL: CFST Containment RED path exists Basis:[These thre&held are for- P-0 WRs uin'g, cr-itcal SafetY =FUctio. StatUe Tce (CSFS'T)g and funtina-l retoer-ation Proedure..

For m..e nformat'-i, W refer to SectioE 3.9 9f RED path indicates an extreme challenge to the safety function derived from appropriate instrument readings and/or sampling results, and thus represents a potential loss of containment.

Conditions leading to a CGontainment RED path result from RCS barrier and/or Fuel Clad Barrier Loss. Thus, this threshold is primarily a discriminator between Site Area Emergency and General Emergency representing a potential loss of the third barrier.There is no Loss threshold associated with this item.Explanation/Discussion/Definitions:

Critical Safety Function Status Tree (CFST) Containment RED path exists if Containment pressure is greater than or equal to 47 psig. The Containment RED path is in the Containment Environment CFST illustrated in Attachment 2, page 9.Containment pressure of this magnitude results from RCS barrier loss or a faulted S/G inside Containment and signifies an extreme challenge to the Containment.

For this condition, all Containment isolations, as well as automatic Containment Spray and CFCU "low speed" operation should be initiated before this threshold is reached.The Containment barrier is considered potentially lost at 47 psig even though the Containment yield strength is much higher that 47 psig. Thus, this threshold is primarily a discriminator Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB1-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 between a Site Area Emergency and a General Emergency (i.e., a potential loss of the third barrier).CFST status will not be used for event classification until the Control Room staff has implemented the CFSTs.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 1.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.05 Containment Environment Status Tree 3. UFSAR 6.2 Containment Systems 4. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB1-P SGS ECG -EAL Technical Bases EP-SC-111-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation CFSTs Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB2-P (2 points)EAL: CFST Core Cooling RED path exists AND Restoration procedure 1(2)EOP-FRCC-1 NOT effective within 15 minutes Basis: See discussion below.[This EAL she.ý,4ul or ,.thor (sito specifc. indications thot mayI iI~~~i~ Ipo.~ # po ll :onsr .i lJL .I l. / ,I& I, from -roea or V..t -tion monitors in contanm nt ,nuu,,oro0t....conigu.us bu.igdigs.

if site moer-lnbv o -tino Pmcedurer nrvide for von inn of tho -contoinr...f durin' on a ..mernorn'-"G G 1'0nr f;rr r'-jkc'rrrfi 0ll /1 ~ ;/- FnI i CA! k ^--~, , i W k ;.-,-It i e4 rJ iF -containm~ent ba;rr~zr.

7Th-S EAL ShOU1d be declared as soonP as such venting is 14MMINEWT.

er rn g n~gg -r i 4 -cr i,,rn~'., -,.,.,,.a;--i~,,,--,.r nm -41, #-t-s.'-JI lL~A gggggg.jgg, vs., g ggg I L4'...'rIryin~zI nffIgnrg*

Irc' *I , -'-UUfVU1-V clutlullo to t:WtC2oort1VU ft! VVI", I- ..1 Explanation/Discussion/Definitions:

CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs. The Core Cooling CFST is illustrated in Attachment 2, page 4.This threshold is redundant to Containment Barrier Potential Losses CB3-P and CB-4P.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 1.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Tree -F.02 Core Cooling Status Tree 3. UFSAR 6.2 Containment Systems 4. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CB2-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CB2-P SGS ECG -EAL Technical Bases EP-SC-111-223 This page intentionally blank Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CB2-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Core Exit TCs Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB3-P (2 points)EAL: Basis: There is no Loss threshold associated with this item.The conditions in these thresholds represent an IMMINENT core melt sequence which, if not corrected, could lead to vessel failure and an increased potential for containment failure. In conjunction with the Core Cooling and RCS Leakage criteria in the Fuel and RCS barrier columns, this threshold would result in the declaration of a General Emergency

-- loss of two barriers and the potential loss of a third. If the function restoration procedures are ineffective, there is no "success" path.The function restoration procedures are those emergency operating procedures that address the recovery of the core cooling critical safety functions.

The procedure is considered effective if the temperature is decreasing or if the vessel water level is increasing.

[For units using the CSF, status tree&, a direct to these status tree, ca- madle i h effoctivpness o-f the- re-stor-ation proc~edures is also evaluated as stated below.][Seer.e acident se, (e.g., NUREG- 1150) have ... ,lud.ed that fun,,.,-restoraLofrn prFOeures Gapn arr-Fest core gra n h the reacort f.tr vessel in a s',g,,ialf fraction of the core damage scenarios, and that the likelihood of containment failure is ver-y small i these events. Given this, it is approepriate to provide a reasognable period to allow function restoration proced'I r~ c to9 aF~s the GO- Melt &eq'eP~e Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB3-P SGS ECG -EAL Technical Bases EP-SC-111-223 Whether or not the procedures will be effective should be apparent within 15 minutes. The Emergency DiFectO-eCoordinator should make the declaration as soon as it is determined that the procedures have been, or will be ineffective.-P-tenRtwil LGss Threshold R[The reactor- Vesac! !eVe! GhGacn sheuldl be con &stent'AWith the c rncgEncGY roe-ponc guides aplcble 'I_ Ihe faility.]Explanation/Discussion/Definitions:

If core exit thermocouple (CET) readings are greater than 1,200°F, Fuel Clad barrier is lost.CETs provide an indirect indication of fuel clad temperature by measuring the temperature of the reactor coolant that leaves the core region. Although clad rupture due to high temperature is not expected for CET readings less than the threshold, temperatures of this magnitude signal significant superheating of the reactor coolant and core uncovery.

Events that result in CET readings above the loss threshold are severe accidents and are a severe accident management "Badly Damaged (BD)" condition.

The BD descriptor signifies possible core overheating to the point that clad ballooning/collapse may occur and portions of the core may have melted.Severe accident analysis has concluded that functional restoration procedures can arrest core degradation within the Reactor Vessel in a significant fraction of the scenarios, and that the likelihood of Containment failure in these scenarios is small. It is appropriate; therefore, to allow a reasonable period of time for the functional restoration procedures to arrest the core melt sequence.

The functional restoration procedure, 1(2)-EOP-FRCC-1, is the emergency operating procedures that address the recovery an inadequate core cooling condition.

Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 3.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree 3. 1(2)-EOP-FRCC-1 Response to Inadequate Core Cooling Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB3-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Core Exit TCs Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB4-P (2 points)EAL: Table F-1 RVLIS Thresholds RVLIS RCPs Full Range 39% None 44% 4 30% 3 Dynamic Range 20% 2 13% 1 Basis: There is no Loss threshold associated with this item.The conditions in these thresholds represent an IMMINENT core melt sequence which, if not corrected, could lead to vessel failure and an increased potential for containment failure. In conjunction with the Core Cooling and RCS Leakage criteria in the Fuel and RCS barrie Barrier columns, this threshold would result in the declaration of a General Emergency

-- loss Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CB4-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 of two barriers and the potential loss of a third. If the function restoration procedures are ineffective, there is no "success" path.The function restoration procedures are those emergency operating procedures that address the recovery of the core cooling critical safety functions.

The procedure is considered effective if the temperature is decreasing or if the vessel water level is increasing.

[o r- uits- usig th CSF statu. trees,~ a dre,,- GOp'agOn to thOe Status trees can b made if the e ; ..tiveness of the resto.-raion prcedure.

is e evaluated as stated below.][Severe occidenqt apa44ses ,-URE 1150) have conGIclued that function re ta, l Jiepoce dur-ee can a~rrest GG, degrodatiOP

~within the reactor y vesel iP S~gg~ i"ani fra't;-n of the_ cre damage enari,,-o,;,, and that the of containment falure- is ve..function reetoration.

procedures to arrest the core melt seqeg'nce.

Whether or not the procedures will be effective should be apparent within 15 minutes. The Emergency DrectGo-rCoordinator should make the declaration as soon as it is determined that the procedures have been, or will be ineffective.

M : 11I-I-W. IliM A4-PA4- A 6 1-, ---- -0:4 A[The reactor h / e- G r -ee guides applicable to the facit.]Explanation/Discussion/Definitions:

This threshold indicates subcooling has been lost (CET readings > 700 0 F), the core is uncovered and some fuel clad damage may be occurring.

The Table F-1 RVLIS thresholds are used in the CFSTs to signal core uncovery and are, therefore, indication of loss of coolant inventory.

If the RVLIS thresholds are exceeded, a core covered condition cannot be confirmed.

Severe accident analysis has concluded that functional restoration procedures can arrest core degradation within the Reactor Vessel in a significant fraction of the scenarios, and that the likelihood of Containment failure in these scenarios is small. It is appropriate; therefore, to allow a reasonable period of time for the functional restoration procedures to arrest the core melt sequence.

The functional restoration procedure, I(2)-EOP-FRCC-1, is the emergency operating procedures that address the recovery an inadequate core cooling condition Definitions:

Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CB4-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 3.B 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.02 Core Cooling Status Tree 3. 1(2)-EOP-FRCC-1 Response to Inadequate Core Cooling Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CB4-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Radiation Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB5-P (2 points)EAL: Containment radiation monitor 1(2)R44A or 1(2)R44B reading > 2000 Rlhr Basis: There is no Loss threshold associated with this item.The site reading is a value which indicates significant fuel damage well in excess of the thresholds associated with both loss of Fuel Clad and loss of RCS banzie-sBarriers.

As stated in NEI 99-01 Section 3.8, a major release of radioactivity requiring off-site protective actions from core damage is not possible unless a major failure of fuel cladding allows radioactive material to be released from the core into the reactor coolant.Regardless of whether Ceontainment is challenged, this amount of activity in CGontainment, if released, could have such severe consequences that it is prudent to treat this as a Ppotential Uoss of Ceontainment, such that a General Emergency declaration is warranted.

[NURE=G 122, , o÷ o;-,,. n , D ....... Ro , e ... ,.,o Pow,-r Plant Accidents-, "indice t- a -Ich conPditions do not oxs hnthI amoGUnt Of clad age is less than 20%. Uless there is a (Site specific) ahnh a ,', ai Th Ha CpciyTepraue Limit (HCTL) is the highes-upeso Pee -emperatuFe fr..W. I,,hi,"h :E::Rgen.Y RPV DepressFurization Will nEot raise Suppressio c-hamber, temperature above the mnaximum tomperature capability Ef h suppressio chamber and equipment within the suppre.SSi.n chamber which may be require t ope1ae when th RPV is pressurized, Suppression chamber pressure above Primary' tanment Pressure Limit A, while the rFate o energy transfer the RPV to the containment is greater than the capacity of the containment Vent.Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CB5-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 Thc HCTL a fUnction of RPV pressure and suppression pool water lcvel. It is utilized to preclude failure of the containment and equipment in the containment necessar,'

for the safe shutdown of the plant and therefore, the inability to maintain plant parameters below the limit constitutes a potential loss of containment.

Explanation/Discussion/Definitions:

1(2)R44A and 1(2)R44B are the Containment High Range area radiation monitors.

The threshold value of 2000 R/hr has been calculated assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with 20% fuel clad damage into the Containment atmosphere.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 6.A 2. Calculation by Nuclear Fuels Group file title DS1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 2/10/95 Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CB5-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 This page intentionally blank I I Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CB5-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB6-P (2 points)EAL: Containment pressure > 47 psig and rising Basis: I m-rL.__- __.-.- A The site-specific pressure is based on the containment design pressure.Explanation/Discussion/Definitions:

The specified Containment pressure (47 psig) is the Containment design pressure.

Proper actuation and operation of the Containment heat removal system when required should avoid Containment pressures in excess of this threshold.

The threshold is therefore indicative of a loss of both RCS and Fuel Clad barriers in that it should not be exceeded without severe core degradation (metal-water reaction) or failure to trip in combination with RCS breach. This condition would be expected to require the declaration of a General Emergency.

Containment Pressure is used as a Containment Barrier threshold in addition to the CFST thresholds to address events in which the CFSTs may not yet be in use.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 2.A 2. 1(2)-EOP-CFST-1 Critical Safety Function Status Trees -F.05 Containment Environment Status Tree 3. Salem EOP Setpoint Basis Document -Vendor Doc. #320832 Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB6-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB6-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB7-P (2 points)EAL: Indications of > 4% H 2 inside Containment Basis: n : I- I-rL. __L_ 1_J A nd of A4 In s ide Cn i nment Existence of an explosive mixture means a hydrogen and oxygen concentration of at least the lower deflagration limit curve exists. The indications of potential loss under this EAL corresponds to some of those leading to the RED path in lSos thrcshld-1-AContainment barrier Potential Loss ALCB1_-Pabo.v and may be declared by those sites WSi-g SFST-s.Explanation/Discussion/Definitions:

When hydrogen concentration in the Containment atmosphere exceeds 4%, the possibility of an explosive mixture exists. Elevated hydrogen concentrations are likely to be present in the Containment only as a result of an inadequate core cooling, substantial metal-water reaction and a breach of the RCS barrier.A 4% mixture of H 2 with normal Containment atmosphere represents the deflagration lower limit. Any subsequent ignition and burn of this level mixture releases a substantial amount of energy that must be absorbed by the Containment structure, which is already under stress due to the Loss of the RCS Barrier.Elevated Containment atmosphere hydrogen concentration is alarmed at > 2% by overhead annunciator C-23, CNTMT H 2 LVL HI.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB7-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 2.B 2. 1(2)-EOP-FRCC-1 Response to Inadequate Core Cooling -Basis Document (pg 16)3. Salem EOP Setpoint Basis Document -Vendor Doc. #320832 4. Sl(S2).OP-AR.ZZ-0003(Q)

OHA C-23, CNTMT H 2 LVL HI Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB7-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

F -Fission Product Barrier Degradation Inventory Initiating Condition:

Mode Applicability:

EAL# & Point Value: EAL: Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB8-P (2 points)Containment pressure > 15 psig AND EITHER of the following:

NO Containment Spray Train in service AND< 5 CFCUs running in low speed* One Containment Spray Train in service AND< 3 CFCUs running in low speed Basis: Potential Loss Threshold C This threshold represents a PEpotential Lloss of Ceontainment in that the Ceontainment heat removal/depressurization system is (e.g., conta;inment Sprays, ice con.Rdenser fans, et.., but not iGncluding containmen.

t venting strategies) are either lost or performing in a degraded manner, as indicated by Ceontainment pressure greater than the setpoint at which the equipment was supposed to have actuated.Explanation/Discussion/Definitions:

A Containment pressure rise above 15 psig (the Containment Spray initiation setpoint)indicates a major release of energy to the Containment.

No Containment Spray with fewer than five Containment Fan Coil Units (CFCUs) running in low speed or only one train of Containment Spray in service with fewer than 3 CFCUs running in low speed indicates a condition in which systems designed for Containment heat removal and depressurization do not have the capacity to maintain Containment pressure below the structural design limit.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB8-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 The Containment Fan Cooling System is designed to circulate and cool the Containment atmosphere in the event of a LOCA and thereby ensures that Containment pressure will not exceed its design value. Five fan-cooler units are capable of transferring heat from the Containment atmosphere at the post-accident design conditions.

The UFSAR accident analyses determined a minimum of three fan-cooler units with at least one Containment Spray train is needed to maintain Containment integrity.

Either of two Containment Spray trains containing a pump, associated valving and spray headers are independently capable of delivering 2,600 gpm.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 2.C 2. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 3. SGS Technical Specifications 3.6.2.1 Spray Additive System 4. SGS Technical Specifications 3.6.2.3 Containment Cooling System 5. UFSAR 6.2.2.1 Containment Spray System 6. UFSAR 6.2.2.2 Containment Fan Cooling System Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB8-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Judgment Potential Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB9-P (2 points)EAL: ANY condition in the opinion of the Emergency Coordinator that indicates potential loss of the Containment barrier Basis: Thisese thresholds addresses any other factors that are to be used by the E,,Rergency

....eto.Emergency Coordinator in determining whether the Containment barrier is loste-potentially lost. In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in Ern.rgencY Dir.....Emerqency Coordinator judgment that the barrier may be considered le0t- r-potentially lost.The Containment barrier should not be declared lest-er-potentially lost based on exceeding Technical Specification action statement criteria, unless there is an event in progress requiring mitigation by the Containment barrier. When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS) the Containment barrier status is addressed by Technical Specifications.

Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the Containment barrier is potentially lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences.

Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance.

Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB9-P SGS ECG -EAL Technical Bases EP-SC-11 11-223 Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of AC power (Station Blackout) and ATWT EALs to assure timely emergency classification declarations.

Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Potential Loss 8.A Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB9-P SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CBI-L (3 points)EAL: Basis:.Loss Thresholds A and B Rapid unexplained loss of pressure (i.e., not attributable to containment spray or condensation effects) following an initial pressure increase from a primary or secondary high energy line break indicates a Lioss of Ceontainment integrity.

pressure and sump levels should increase as a result of mass and energy release into containment from a LOCA. Thus, sump level or pressure not increasing indicates containment bypass and a loss of conRtainment integrity.

This indicator relies on operator recognition of an unexpected response for the condition and therefore does not have a specific value associated with it. The unexpected response is important because it is the indicator for a Containment bypass condition.

Explanation/Discussion/Definitions:

The term "Unexplained" signifies the pressure drop is not a result of operator actions taken to reduce Containment pressure.

The term "rapid" indicates the Containment breach is relatively large.For cases in which secondary coolant provides the source of energy that raised Containment pressure, a faulted Steam Generator is possible.

This event would require actions in 1(2)-EOP-LOSC-1 to isolate the Main Steam lines, maintain intact Steam Generators for an RCS Heat Sink, minimize Containment pressure, and minimize RCS cooldown.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB1-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Barrier Loss 2.A 2. UFSAR Table 15.4-22 LOCA Containment Response Results (Loss of Offsite Power Assumed)3. UFSAR Figures 15.4-43a, b and c Containment Pressure (varying initial conditions)

4. UFSAR Figure 15.4-44 Containment Pressure 5. 1(2)-EOP-LOSC-1 Loss of Secondary Coolant Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CBI -L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB2-L (3 points)EAL: Containment pressure or sump level response NOT consistent with LOCA conditions Basis: Less Thresholds&A nd8 Rapid unexplained loss Of pressure (i.e., not attributable to) containment spray or condensationf,.ollow-, "Ing.. an ial from a primary or seGodary high energy li break indeates a loss o~f containment integrit.

Containment pressure and sump levels should increase as a result of mass and energy release into Ceontainment from a LOCA. Thus, sump level or pressure not increasing indicates Ceontainment bypass and a Lioss of Containment integrity.

This indicator relies on operator recognition of an unexpected response for the condition and therefore does not have a specific value associated with it. The unexpected response is important because it is the indicator for a Ceontainment bypass condition.

Explanation/Discussion/Definitions:

A LOCA is expected to result in a significant Containment pressure rise. This leak rate should result in the accumulation of RCS inventory in the Containment sump as the level rises. A lack of expected Containment sump level response or Containment pressure not rising indicates that the Containment barrier has been bypassed.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Barrier Loss 2.B 2. UFSAR Table 15.4-22 LOCA Containment Response Results (Loss of Offsite Power Assumed)3. UFSAR Figures 15.4-43a, b and c Containment Pressure (varying initial conditions)

4. UFSAR Figure 15.4-44 Containment Pressure Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 This page intentionally blank Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB2-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Inventory Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB3-L (3 points)EAL: RUPTURED SG that is also FAULTED outside of Containment Basis: Potential LoSS Threshold A The Lioss threshold recognizes that SG tube leakage can represent a bypass of the Containment barrier as well as a Ltoss of the RCS barrier.Users should realize that the twO lOss th-csh-ldsThis Loss threshold and Containment Loss CB4-L could be considered redundant.

This was reco.gnized during the development process.The inclusion of an threshold that uses terms that are commonly used in Emergency Operatinq Procedure commonl.y used terFmos like "RUPTURED and FAULTED" adds to the ease of the classification process and has been included based on this human factor concern.This thFeshold results in a NlUE for smaller breaks that; (1) do not exceed the -nrmal charging capacity threShld in RCS leak rate barrier Potential Loss threshold, or (2) do not result in EGGS actuatier in RCS SG tube rupture barrier L oss ehrcshld.

For larger breaks, RCS barrier threshold criteria would result in an Alert. For SG tube ruptures which may involve multiple steam generators or UNISOLABLE secondary line breaks, this threshold would exist in conjunction with RCS barrier thresholds and would result in a Site Area Emergency.

Escalation to General Emergency would be based on "Potential Loss" of the Fuel Clad Barrier.Loss Threshold A This threshold addresses the condition in which a RUPTURED steam generator is also FAULTED. This condition represents a bypass of the RCS and containment barriers and is a subset of the Seeeed-threshold CB4-L. In conjunction with RCS leak rate barrier loss threshold, this would always result in the declaration of a Site Area Emergency.

Explanation/Discussion/Definitions:

Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 This threshold is intended to include all flow paths of Contaminated secondary coolant to the environment directly or through systems which exhaust to the Plant Vent (e.g.; leakage to the Auxiliary Building ventilation system). An exception would be if the EOPs require steaming the ruptured Steam Generator to the main condenser.

The main condenser off-gas (R1 5) pathway is excluded from this EAL provided the release is both controlled and monitored.

Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CB3-L SGS ECG -EAL Technical Bases EP-SC-11 11-223 Definitions:

RUPTURED: (PWRs) In a steam generator, existence of primary-to-secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

FAULTED: (PWRs) In a steam generator, the existence of secondary side leakage that results in an uncontrolled drop in steam generator pressure or the steam generator being completely depressurized.

UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Barrier Loss 4.A 2. 1(2)-EOP-SGTR-1 Steam Generator Tube Rupture 3. 1(2)-EOP-SGTR-3 SGTR with LOCA -Subcooled Recovery Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CB3-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

F -Fission Product Barrier Degradation Inventory Initiating Condition:

Mode Applicability:

EAL# & Point Value: EAL: Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB4-L (3 points)Primary-to-secondary leakrate > 25 gpm AND UNISOLABLE steam release from affected SG to the environment Basis: Dotential oIs Threshold A The Lloss threshold recognizes that SG tube leakage can represent a bypass of the Containment barrier as well as a Lioss of the RCS barrier.Users should Ire-alize that the two loss thresho This Loss threshold and Containment Loss CB3-L could be considered redundant.

This was during the development proGeSs.-" -I M-I tiiD iI .i T -,.4 i A 1 11' = Mi, l -A ---C 44.- -l ..:-,4,;- -- 4 1- --' L-. --l..IIt..ALILAII LILA LILII I t.lI LILILILJL.I LAI ILl I ILALI LILILII I incldedbase onthis human factor concern.-This threshold results in a NGUE for smaller breaks that; (1) do not exceed the normal charging capacity threshold in RCS leak rate barrier Potential Loss thesheld.RB3-P, or (2) do not result in ECCS (Sl) actuation in RCS SG tube rupture barrier Loss thweshe!dRB3-L.

For larger breaks, RCS barrier threshold criteria would result in an Alert. For SG tube ruptures which may involve multiple steam generators or UNISOLABLE secondary line breaks, this threshold would exist in conjunction with RCS barrier thresholds and would result in a Site Area Emergency.

Escalation to General Emergency would be based on "Potential Loss" of the Fuel Clad Barrier.I -Tk.'-.-Irj D This threshold addresses SG tube leaks that exceed 25 4-0-gpm in conjunction with an UNISOLABLE release path to the environment from the affected steam generator.

The Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 threshold for establishing the UNISOLABLE secondary side release is intended to be a prolonged release of radioactivity from the RUPTURED steam generator directly to the environment.

This could be expected to occur when the main condenser is unavailable to accept the contaminated steam (i.e., SG tube rupture with concurrent loss of off-site power and the RUPTURED steam generator is required for plant cooldown or a stuck open relief valve). If the main condenser is available, there may be releases via air ejectors, gland seal exhausters, and other similar controlled, and often monitored, pathways.

These pathways do not meet the intent of an UNISOLABLE release path to the environment.

These minor releases are assessed using EALs in Category R, Abnormal Rad Levels / Radiological Effluent IGs.[The leakage tshi ÷' old.for this threshold has been i, I .rease, K444h £,,;o;i, 3. n earler-r-e vsiop, the thr-esholdl was leakage grFeater than TIS allow-able.

Sincoe the p~e many. plants have implemented r-edU~ed SeaM rg enera tor- T43 ii (e.g., 150 gpdl) as a defensEe in dlepth a&&gciated with alternate steam genera ter- plugging Gr~terna.

The 150 gp~threshold is deemed too low for use as an emergency threshold.

A pr-essure boundar-y leakage of 10 gpm was used as the threshoidin 1QCS95, RCS Leakage, and is deemed appr-opriate fo!this Explanation/Discussion/Definitions:

Definitions:

RUPTURED: (PWRs) In a steam generator, existence of primary-to-secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Barrier Loss 4.B Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB4-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: EAL: F -Fission Product Barrier Degradation Other Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB5-L (3 points)Failure of ALL valves in ANY one line to close AND Direct downstream pathway to the environment exists after Containment isolation signal (Note 8)Note 8: A direct downstream release is a pathway from the Containment to any environment outside the Containment when Containment or system isolation is required due to: a safety injection signal, Containment pressure greater than 4 psig, or a VALID containment ventilation isolation signal and the pathway cannot be isolated from the Control Room.Basis: This threshold addresses incomplete containment isolation that allows direct release to the environment.

The use of the modifier "direct" in defining the release path discriminates against release paths through interfacing liquid systems. The existence of an in-line charcoal filter does not make a release path indirect since the filter is not effective at removing fission product noble gases. Typical filters have an efficiency of 95-99% removal of iodine. Given the magnitude of the core inventory of iodine, significant releases could still occur. In addition, since the fission product release would be driven by boiling in the reactor vessel, the high humidity in the release stream can be expected to render the filters ineffective in a short period.There is no Potential Loss threshold associated with this item.Explanation/Discussion/Definitions:

Indications of Containment failure may be evident without the exact pathway being understood at the time of the failure. If the Containment or part of the RCS is required to be isolated and Salem Page 1 of 4 Rev. 0 (draft E)EAL#: CB5-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 there are VALID indications that the Containment is not isolated, the Containment barrier should be considered lost.Area Radiation monitor alarms that exceed normal monitor indications without a reason to expect another source such as a gas decay tank, spill, piping shine or fuel handling problem, indicate a loss of the Containment.

Area temperature alarms, rising sump level indications or unexpected system flow indications outside Containment may also indicate a loss of the Containment.

If the Containment Barrier is lost without a loss of the Fuel Clad Barrier, effluent radiation readings may not increase significantly.

Unexpected area temperature alarms, unexpected flow rates or sump level increases outside of Containment, however, may provide the indications that the Containment atmosphere is no longer isolated.

In addition, the term "to the environment" is intended to include any leakage that cannot be isolated either directly or through systems that exhaust to the Plant Vent (e.g., leakage to the Auxiliary Building Ventilation System) or directly to any other area outside the Containment.

A safety injection, high Containment pressure or a Containment vent isolation signal represents a situation that requires the Containment to be isolated from the outside environment.

As indicated in Note 8, this EAL allows for valve closure from the Control Room, prior to event classification, to isolate any system not completely isolated.

Leakage cannot be isolated from the Control Room refers to valve(s) that did not completely close when demanded (either automatically or manually).

This includes Motor Operated Valves not controlled by isolation logic but are manually controlled from the Control Room. For example, if the isolation logic fails to cause valve closure but operator actions implemented in the Control Room successfully isolates the Containment breach path, classification under this EAL is NOT WARRANTED.

Although this EAL ALLOWS for valve closure from the Control Room, the time to attempt closure and make a decision if containment leak isolation was successful RUNS CONCURRENTLY with the EAL 15-minute assessment clock.* If, during the EAL 15-minute assessment period attempts from the Control Room to isolate the containment ARE SUCCESSFUL then, this EAL is NOT exceeded and classification per this EAL should NOT be made." If, during the EAL 15-minute assessment period attempts from the Control Room to isolate the containment ARE NOT SUCCESSFUL then, this EAL is exceeded and classification should be made at that time. There is no need to wait the full 15 minutes.* If near the end of the 15 minute assessment period and the control room staff has not been able to attempt containment isolation or the EC is not convinced that an isolation attempt has been successful, then this EAL is exceeded and classification should be made at or before the 15-minute assessment time expires.Salem Page 2 of 4 Rev. 0 (draft E)EAL#: CB5-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 Definitions:

VALID: An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Barrier Loss 5.A 2. SGS Technical Specifications 3.6.3 Containment Isolation Valves 3. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 4. 1(2)-EOP-LOCA-6 LOCA Outside Containment Salem Page 3 of 4 Rev. 0 (draft E)EAL#: CB5-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: CB5-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 EAL Category: Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Point Value: F -Fission Product Barrier Degradation Judgment Loss of Containment 1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown CB6-L (3 points)EAL: ANY condition in the opinion of the Emergency Coordinator that indicates loss of the Containment barrier Basis: Thisese thresholds addresses any other factors that are to be used by the EmeFgene DieGte Emergency Coordinator in determining whether the Containment barrier is lost-ei.In addition, the inability to monitor the barrier should also be incorporated in this threshold as a factor in Emergency DireGtorEmerqency Coordinator judgment that the barrier may be considered lost-or potentially lost.The Containment barrier should not be declared lost or potentially based on exceeding Technical Specification action statement criteria, unless there is an event in progress requiring mitigation by the Containment barrier. When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS) the Containment barrier status is addressed by Technical Specifications.

Explanation/Discussion/Definitions:

The Emergency Coordinator judgment threshold addresses any other factors relevant to determining if the Containment barrier is lost. Such a determination should include IMMINENT barrier degradation, barrier monitoring capability and dominant accident sequences.

Barrier degradation exists if the degradation will likely occur within two hours based on a projection of current safety system performance.

Barrier monitoring capability is decreased if there is a loss or lack of reliable indicators.

This assessment should include instrumentation operability concerns, readings from portable instrumentation and consideration of offsite monitoring results.* Dominant accident sequences lead to degradation of all fission product barriers and likely entry to the EOPs. The Emergency Coordinator should be mindful of the Loss of Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CB6-L SGS ECG -EAL Technical Bases EP-SC-1 11-223 AC power (Station Blackout) and ATWT EALs to assure timely emergency classification declarations.

Definitions:

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, Table 5-F-3 Containment Loss 8.A Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CB6-L EALs for: Cold Shutdown Conditions SGS ECG -EAL Technical Bases EP-SC-111-224 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Cold Shutdown / Refuel System Malfunction 1 -Loss of AC Power AC power capability to vital buses reduced to a single power source for 15 minutes or longer such that any additional single failure would result in complete loss of AC power to vital buses 5 -Cold Shutdown, 6 -Refueling CUI.1 -UNUSUAL EVENT Loss of 4.16 KV Vital Bus Power Sources (Offsite and Onsite) which results in the availability of only one 4.16 KV Vital Bus Power Source (Offsite or Onsite)AND_ 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: The condition indicated by this FG-EAL is the degradation of the off-site and on-site AC power systems such that any additional single failure would result in a station blackout.

This condition could occur due to a loss of off-site power with a concurrent failure of all but one emergency diesel generator to supply power to its eme-ren-vital busses. The subsequent loss of this single power source would escalate the event to an ALERT in accordance with GA-3EAL CA1.1.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of power.Explanation/Discussion/Definitions: "Availability" means the power source can be aligned to provide power to a vital bus within 15 minutes or is currently supplying power to at least one vital bus.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CU 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-224 The availability of EDGs that have not been challenged to start during degradation of AC power sources to the 4KV vital buses should be based on meeting Technical Specification action requirements for loss of offsite AC power sources.The AC power distribution is summarized in Attachment 2, page 2.Emergency Classification escalates to an ALERT under EAL CA1.1 based on a loss of all offsite and all onsite AC power to all 4KV vital buses.This cold condition UNUSUAL EVENT EAL is equivalent to the hot condition ALERT EAL SA1.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -CU3 Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1.2 Electrical Power Systems -Shutdown 7. SGS Technical Specifications 3.8.2.2 AC Distribution

-Shutdown 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10.Sl(S2).OP-AB.LOOP-0001(Q)

Loss of Off-Site Power 11.S1(S2).OP-AB.4KV-0001(Q)

Loss of 1A 4KV Vital Bus 12. S (S2).OP-AB.4KV-0002(Q)

Loss of 1 B 4KV Vital Bus 13.S1(S2).OP-AB.4KV-0003(Q)

Loss of 1C 4KV Vital Bus Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CUl.1 SGS ECG -EAL Technical Bases EP-SC-111-224 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 1 -Loss of AC Power Loss of all offsite and all onsite AC power to vital buses for 15 minutes or longer 5 -Cold Shutdown, 6 -Refueling, D -Defueled EAL# & Classification Level: CAI.1 -ALERT EAL: Loss of all Power (Onsite and Offsite) to all 4KV Vital Buses AND> 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: Loss of all AC power compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal, Spent Fuel Heat Removal and the Ultimate Heat Sink (Service Water).The event can be classified as an ALERT when in cold shutdown, refueling, or defueled mode because of the significantly reduced decay heat and lower temperature and pressure, increasing the time to restore one of the emergency-vital busses, relative to that specified for the SITE AREA EMERGENCY EAL.Escalating to SITE AREA EMERGENCY, if appropriate, is by EALs in Category R, Abnormal Rad Levels / Radielegi-al Effluent4Gs.

Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.ExplanationlDiscussionlDefinitions:

The intent of this EAL is to classify degraded AC power events that result in a loss of all offsite power sources (13.8 KV) to the 4KV vital buses along with a loss of all onsite power sources (EDGs).Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CA 1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-224 The AC power distribution is summarized in Attachment 2, page 2.This cold condition ALERT EAL is equivalent to the hot condition SITE AREA EMERGENCY EAL SS1.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05 -CA3 Example EAL #1 2. UFSAR Figure 8.2-2 500 kV Switchyard Diagram 3. UFSAR Figure 8.3-1 Auxiliary Power System Diagram 4. UFSAR 8.1.1 Utility Grid System and Interconnections

5. UFSAR 8.3.1 Power 6. SGS Technical Specifications 3.8.1.2 Electrical Power Systems -Shutdown 7. SGS Technical Specifications 3.8.2.2 AC Distribution

-Shutdown 8. 1(2)-EOP-TRIP-1 Reactor Trip or Safety Injection 9. 1(2)-EOP-LOPA-1 Loss of All AC Power 10. S1 (S2).OP-AB.LOOP-0001 (Q) Loss of Off-Site Power 11. S1(S2).OP-AB.4KV-0001 (Q) Loss of 1A 4KV Vital Bus 12. S1 (S2).OP-AB.4KV-0002(Q)

Loss of 1B 4KV Vital Bus 13. S1 (S2).OP-AB.4KV-0003(Q)

Loss of lC 4KV Vital Bus Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CA1.1 SGS ECG -EAL Technical Bases EP-SC-1 11-225 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: C -Cold Shutdown / Refuel System Malfunction 2 -Loss of DC Power Loss of required DC power for 15 minutes or longer 5 -Cold Shutdown, 6 -Refueling CU2.1 -UNUSUAL EVENT EAL:< 114 VDC bus voltage indications on All 125 VDC vital buses for _.15 minutes (Note 3)OR< 25 VDC bus voltage indications on both 28 VDC vital buses for -15 minutes (Note 3) AND loss of control of Safety Related Equipment from the Control Room has been confirmed Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: The purpose of this I-CEAL and its associated EALs is to recognize a loss of DC power compromising the ability to monitor and control the removal of decay heat during Cold Shutdown or Refueling operations.

[This EAL is .dt,-d, to be !,t--',, tory in asmu, h as the operating ,r.w may nt, h4ave fffr~ cff V H;::ug_"tfu;;

dfitt tu;;uff; (i ; &I ;;&~tft t v:Ut tu f Vtruffu tb uff' L)Z. .J I I fR/anpts wigl roeutinlype for mainten-Rene o a Tr~ain related basi's dur.'g shutdown periods Th7rqu-ird use arc the menimm aleIowed by Technica!

SpeccficationS f the modo G.peiratd n7-It is intended that the loss of the operating (operable) train is to be considered.

If this loss results in the inability to maintain cold shutdown, the escalation to an ALERT will be per GA4EAL CA4*1.[(Site specifi) bus voltage should be base d on the mRnimum bus vo!ltge, Peessy for-the operati4on of safety related equipment.

This voltage value should incroaeamargn of a least 15 m~inutes of operation begfoe the onset of inability to ope~ra9te those_ loeads. ThS :s '0age is usually n-e-arth-e m-1inimum voltag sole Getd wh3en battery sizing is perqfoms d. Typicallyth

value for- the entire battery set is approximately 105 VDC. For a 60 cell stin;g of batteries th-e Gcell vol-tage is typic al 75 Vofl& cell. For a 58 string battery set the minimum voltaGe i_typiGcay 181 ý!Vots per- ell.]Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-225 Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Explanation/Discussion/Definitions:

The specified bus voltage indications (rounded for readability on Control Room instrumentation) are the minimum voltage requirements for operability of the 125 VDC buses and 28 VDC buses following battery discharge tests. Although continued operation may occur with degraded voltage, these values signify the minimum operable voltages allowed.This UNUSUAL EVENT EAL is the cold condition equivalent of the hot condition loss of DC power SITE AREA EMERGENCY EAL SS2.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, SS3 Example EAL #1 2. SC.MD-ST.125-0004 (Q) 125 Volt Station Batteries 18 Month Service Test and Associated Surveillance Testing Using BCT-2000 3. SC.MD-ST.28D-0004 (Q) 28 Volt Station Batteries 18 Month Service Test and Associated Surveillance Using BCT-2000 4. UFSAR 8.3.2 DC Power 5. SGS Technical Specifications 3.8.2.3 125 Volt DC Distribution

-Shutdown 6. SGS Technical Specifications 3.8.2.5 28 Volt DC Distribution

-Shutdown 7. S1(S2).OP-SO.125-0005 1(2)A 125VDC Bus Operation 8. S1(S2).OP-SO.

125-0006 1(2)B 125VDC Bus Operation 9. Sl(S2).OP-SO.125-0007 1(2)C 125VDC Bus Operation Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CU2.1 SGS ECG -EAL Technical Bases EP-SC-1 11-226 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 3 -RCS Level UNPLANNED loss of RCS inventory 5 -Cold Shutdown EAL# & Classification Level: CU3.1 -UNUSUAL EVENT EAL: RCS leakage results in the inability to maintain or restore RCS level to EITHER: " Pressurizer Level > 17% (cold calibration value)* Within the target band established by procedure (when the level band is established below the pressurizer)

AND>_ 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: This EAL is considered to be a potential degradation of the level of safety of the plant. The inability to maintain or restore level is indicative of loss of RCS inventory.

Relief valve normal operation should be excluded from this tGEAL. However, a relief valve that operates and fails to close per design should be considered applicable to this IG--EAL if the relief valve cannot be isolated.Prolonged loss of RCS Inventory may result in escalation to the ALERT emergency classification level via either EAL CA3.1 or EAL CA4.1.Explanation/Discussion/Definitions:

When Pressurizer (PZR) level drops to 17%, letdown isolates and pressurizer heaters are deenergized.

The Pressurizer cold calibration level is monitored on LI-462. This condition is signaled by overhead annunciator E-36, PZR HTR OFF LVL LO. Cold calibrated Pressurizer level is indicated on computer points and SPDS.Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-226 In Cold Shutdown mode, PZR level may be intentionally lowered below the letdown isolation setpoint (e.g., in preparation to detension the reactor vessel head, etc.). For such evolutions, this EAL is applicable if RCS level cannot be restored and maintained within the prescribed target band specified in operating procedures.

Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CU1 Example EAL #1 2. S1(S2).OP-AR.ZZ-0005(Q)

OHA- E-36, PZR HTR OFF LVL LO 3. S1 (S2).OP-IO.ZZ-0006(Q)

Hot Standby to Cold Shutdown 4. S1(S2).OP-IO.ZZ-0007(Q)

Cold Shutdown to Refueling 5. S1(S2).OP-SO.RC-0005 (Q) Draining the Reactor Coolant System To >101 Foot Elevation 6. S1(S2).OP-SO.RC-0006 (Q) Draining the Reactor Coolant System < 101ft Elevation with Fuel in the Vessel Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CU3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-226 EAL Category:

C -Cold Shutdown / Refuel System Malfunction EAL Subcategory:

3 -RCS Level Initiating Condition:

UNPLANNED loss of RCS inventory Mode Applicability:

6 -Refueling EAL# & Classification Level: CU3.2 -UNUSUAL EVENT EAL: RCS level CANNOT be monitored with a loss of RCS inventory as indicated by ANY unexplained RCS leakage indication, Table C-1 Table C-1 RCS Leakage Indications

Rise in Containment sump pump run frequency* Aux Building sump level rise* PRT level rise* RWST level rise* RCDT level rise* Rise in RCS make-up rate* Observation of RCS leakage that is UNISOLABLE Salem Page 1 of 5 Rev. 0 (draft E)EAL#: CU3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 Basis: This 4I-EAL is a precursor of more serious conditions and considered to be a potential degradation of the level of safety of the plant.Refuelig evolutions that decrease RCS watcr level below the RPV flange are carcfull, planned and procedurally controlled.

An UNPLANNED event that FcsultS in water level ,casreinng bclew the RPV flange, or below the planned RS wateFr level for the given evolution (if the planned RCS watcr level is alrcady the RPV flange), warrants f a NOUE due to the reduced RCS iRnvnt.ry that is available to keep the core eevefed-The allowa'nr Of 1 5 minutes Was be.ause it is reasonable to assume that levl1 an e rbeestored within this time frame us ingne or more of the redundant means of refill that serius conditin `=exists.Continued loss of RCS Inventor;y Will result in escalationR to the ALERT emergency classification level via either CAI or CM4.[The differene between GUl and CU2 deals wth the RCS conditions that ex`s`between GOOd &hUtd`wn and refueling modeS. !n4`= ld &'Utdow`n the RCS wil normaly be 4ntaci and standard RCS invent. and le... monitorig mean, are available.

In the refuel,,`ng mod4e, the RCS is not intact and RP-V level andl invý_Pentry are monpitored by diferent means].EAIL I--This EAL addresses conditions in the Rfefueling mode-_when normal means of core temperature indication and RCS level indication may not be available.

Redundant means of RPV-RCS level indication will normally be installed (including the ability to monitor level visually) to assure that the ability to monitor level will not be interrupted.

However, if all level indication were to be lost during a loss of RCS inventory event, the operators would need to determine that RPV-RCS inventory loss was occurring by observing sump and tank level GhangesTable C-1 indications.

Sump and tank levelTable C-1 iRGheasesRCS leakage indications must be evaluated against other potential sources of leakage such as cooling water sources inside the containment to ensure they are indicative of RCS leakage.Escalation to the ALERT emergency classification level would be via eitther-EAL GA4-CA3.2 or EAL CA4.1.Explanation/Discussion/Definitions:

During refueling, the reactor head and associated RVLIS piping are removed. Visual observation by personnel on the' refuel floor in communication with the Control Room may also provide indication of refueling cavity water level and RCS water level.Salem Page 2 of 5 Rev. 0 (draft E)EAL#: CU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 In this EAL, all level indication is unavailable and the RCS inventory loss must be detected by the leakage indications listed in Table C-1. Level increases must be evaluated against other potential sources of leakage such as cooling water sources inside the Containment to ensure they are indicative of RCS leakage. Visual observation of leakage from systems connected to the RCS in areas inside or outside the Containment that cannot be isolated could be indicative of a loss of RCS inventory.

Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: CU3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CU2 Example EAL #2 2. S1 (S2).OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System 3. UFSAR 5.6.5 Reactor Vessel Water Level 4. UFSAR 7.3.1.1.9 Instrumentation Used During a Loss of Coolant Accident 5. SI(S2).OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 6. S1(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System To >101 Foot Elevation 7. UFSAR Figure 6.3-3 Containment Sump Pit 8. UFSAR 6.3.2.2 Equipment and Component Description (ECCS)9. UFSAR Figure 6.2-17 Containment Isolation Pressurizer Relief Tank Connections

10. S1 (S2).OP-AB.RC-0001 (Q) Reactor Coolant System Leak Salem Page 4 of 5 Rev. 0 (draft E)EAL#: CU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: CU3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 3 -RCS Level UNPLANNED loss of RCS inventory 6 -Refueling EAL# & Classification Level: CU3.3 -UNUSUAL EVENT EAL: UNPLANNED RCS level drop below EITHER of the following:

104 ft (Reactor Vessel flange)* RCS level band (when the RCS level band is established below the Reactor Vessel flange)AND_ 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: This EAL is a precursor of more serious conditions and considered to be a potential degradation of the level of safety of the plant.Refueling evolutions that decrease RCS water level below the RPV-Reactor Vessel flange are carefully planned and procedurally controlled.

An UNPLANNED event that results in water level decreasing below the RPV-Reactor Vessel flange, or below the planned RCS water level for the given evolution (if the planned RCS water level is already below the RPV-Reactor Vessel flange), warrants declaration of a NQUE due to the reduced RCS inventory that is available to keep the core covered.The allowance of 15 minutes was chosen because it is reasonable to assume that level can be restored within this time frame using one or more of the redundant means of refill that should be available.

If level cannot be restored in this time frame then it may indicate a more serious condition exists.Salem Page 1 of 3 Rev. 0 (draft E3)EAL#: CU3.3 SGS ECG -EAL Technical Bases EP-SC-111-226 Continued loss of RCS Inventory will result in escalation to the ALERT emergency classification level via either EAL GA-!CA3.1 or EAL CA4.1.[The diffeFrP.

e between CU! and, CU2 deas with the RCS ,ond1itios that exis betwe GOld shutdoewn and/ re fueling modes. In Gold ShutdoGwn the RC S WiW normally be ntact and standaqrd41 -C invItor an leve moiorn rn ar 4aviable.

1n the re-fue14ng-moede the RGS is not intact and RPV1 love land ~i vn tor-y aemonitored b~y differont means].EAL-#i This EAL involves a decrease in RCS level below the top of the RP-LReactor Vessel flange that continues for 15 minutes due to an UNPLANNED event. This EAL is not applicable to decreases in flooded -a--te--refuelinq cavity level, which is addressed by EAL AW2 EAL-4RU2.1, until such time as the level decreases to the level of the vessel flange.[For BWRs] if RPV Ic..l continue.

to decrease and reaches the Low Low S Actuation Setpint then to CAI would be appropriate.

Explanation/Discussion/Definitions:

104 ft is the Reactor Vessel flange elevation.

RCS water level is normally monitored using the instrument ranges illustrated in Attachment 2, page 10.During refueling, the reactor head and associated RVLIS piping are removed. Visual observation by personnel on the refuel floor in communication with the Control Room may also provide indication of refueling cavity water level and RCS water level.In cold conditions, RCS level may be intentionally lowered below the Reactor Vessel flange (e.g., detensioning the Reactor Vessel head, reduced inventory conditions, etc.). For such evolutions, this EAL is applicable if RCS level cannot be restored and maintained within the prescribed target band.This Cold Shutdown EAL represents the hot condition EAL SU7.1, in which RCS leakage is associated with Technical Specification limits. In cold conditions, these limits are not applicable; hence, the use of RCS level as the parameter of concern in this EAL.Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CU2 Example EAL #1 2. S1(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System to >101 Foot Elevation Salem Page 2 of 3 Rev. 0 (draft E3)EAL#: CU3.3 SGS ECG -EAL Technical Bases 31 SI (S2).OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System 4, UFSAR 5.6.5 Reactor Vessel Water Level 5. UFSAR 7.3.1.1.9 Instrumentation Used During a Loss of Coolant Accident EP-SC-111-226 Salem Page 3 of 3 Rev. 0 (draft E3)EAL#: CU3.3 SGS ECG -EAL Technical Bases EP-SC-111-226 EAL Category:

C -Cold Shutdown / Refuel System Malfunction EAL Subcategory:

3 -RCS Level Initiating Condition:

Loss of RCS inventory Mode Applicability:

5 -Cold Shutdown, 6 -Refueling EAL# & Classification Level: CA3.1 -ALERT EAL: RCS level < 97.5 ft Basis: Thisese EALs serves as a precursors to a loss of ability to adequately cool the fuel. The magnitude of this loss of water indicates that makeup systems have not been effective and may not be capable of preventing further RP-VRCS level decrease and potential core uncovery.

This condition will result in a minimum emergency classification level of an ALERT.EAL 41+i1[The BVVR Low-Lew ECCS Actuation Setpoint/'Level 2A was chosen bccaus ic' 9 tandr setpoint at some available injection systems tar:t-. The PWR Bo--"m ID of the RCS SLevel setpoint was chosen because at this level remote RCS level indication may be lost and loss of suction to decay heat removal systems has 9Gcurremay occur.-The Bottem ID of the R, S Loop should be the level equal to the bottom of the RPV loop penetration (not the lovv peint of the loop).]The inability to restore and maintain level after reaching this setpoint would be indicative of a failure of the RCS barrier.EAL f2-[in the c.ld shutdoWn.

mode, normal R.S lpd RP.. ,e ,, 11, stumentaton Systems wXliluuWaly be a-vai',.abl..

In, the rfhn md nor.., .ma m.n of lvi o may nol bevie .Redundant means of RPV level idcation w48 usually be insta,.d the ability to monitor- level visually) to asueta h biliy to monitor lovei w4# pet be itnhi-Fpted.

Howe_ V'-9F ;al"~ -1 lel gdi~atiOn wer-e to be lot duin a~ lOof RGS invýentor event, the operator" would Peed to deRi*ne that RPV, inventoy loss was by ,b ser,,. g sum and tan- -le va ' ohanges. Sump and tank /evol increases must" be evle a t othe'r potential sout rces of leakage such as cool/n g water sourocsinsdthcoanm ttoeur they are indiative of RCS leakage.]Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-226[The 15 m inute dur.ati.n for the los of Ic .v.l be.ause. it iS half Of the CS01 QSite Area E-mergenlCy EA4L dur-ation.

Significant fuel damage iS not eXpected to occut until the Gore has been uncover-ed 9fo greater than 1 h~our- per- the analysis re-Aferened in th e If RPV-RCS level continues to lower then escalation to SITE AREA EMERGENCY will be via EAL CS3.42.Explanation/Discussion/Definitions:

RCS water level is normally monitored using the instrument ranges illustrated in Attachment 2, page 10.The centerline level of the RCS loop hot leg is at approximately 97 ft and the inside diameter of the hot leg penetration is 29 in. The bottom ID would be 97 ft -29/2 in. or 95 ft 9.5 in.Although NEI desires a level for this threshold that is equal to the bottom of the RCS loop hot leg penetration, the RCS level indication capability does not support detection of a threshold level that low. Mid Loop Level indication is capable of monitoring level to 97.3 ft; so, a setpoint of 97.5 ft has been selected.

Local indication is also available to monitor this level. Continued inventory loss could result in a loss of suction to the RHR System. The inability to restore and maintain level after reaching loop centerline (approximately) would therefore be indicative of a failure of the RCS barrier.EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CA1 Example EAL #1 2. S1 (S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System to >101 Foot Elevation 3. UFSAR Figure 5.1-1 Reactor Vessel Schematic 4. S1(S2).OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 5. UFSAR Figure 6.3-2 & 6.3-3 Containment Sump and Drain Trench & Containment Sump Pit 6. UFSAR 6.3.2.2 Equipment and Component Description (ECCS)7. UFSAR Figure 6.2-17 Containment Isolation Pressurizer Relief Tank Connections

8. S1 (S2).OP-AB.RC-0001 (Q) Reactor Coolant System Leak Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CA3.1 SGS ECG -EAL Technical Bases EP-SC-1 11-226 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 3 -RCS Level Loss of RCS inventory 5 -Cold Shutdown, 6 -Refueling EAL# & Classification Level: CA3.2 -ALERT EAL: RCS level CANNOT be monitored for > 15 minutes with a loss of RCS inventory as indicated by ANY unexplained RCS leakage indication, Table C-1 (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Table C-1 RCS Leakage Indications

Rise in Containment sump pump run frequency* Aux Building sump level rise* PRT level rise* RWST level rise* RCDT level rise* Rise in RCS make-up rate Observation of RCS leakage that is UNISOLABLE Salem Page 1 of 5 Rev. 0 (draft E)EAL#: CA3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 Basis: Thisese EALs serves as a precursors to a loss of ability to adequately cool the fuel. The magnitude of this loss of water indicates that makeup systems have not been effective and may not be capable of preventing further -RPV-RCS level decrease and potential core uncovery.

This condition will result in a minimum emergency classification level of an ALERT.EAL-#4[The BL4R Low Low EGGS Actuation Setpoint!LeveI 2 WaS chOSen bccousc it :s a stan darci&ctpint at wehi.h some available injection ySoy'Ms ao"moatically Start. The PWR Bettom ID of the RCS Loop Setpoint;VaS chosen because at this leýW, repote RCS leý h4 idCgation may be lost an~d 1os8 of SUction to decay h y at repmoval systems ha& occurredf.

Thye Bottom3 Q of the RC Loop Setpoint should be the level eqgualto the bottom of the RPV loop ponetration (not the Iot point of thye loopf The inability to restore and maintain level after reaching this Setpoint would be indicative of a failure of the ROS barrier.L I.#2-[In the CGoold Sshutdown mode, normal RGS level and RPV leve instrumentation systems will usually be available.

In the Rfrefueling mode, normal means of RPV-RCS level indication may not be available.

Redundant means of RPV RGS level indication will usually be installed (including the ability to monitor level visually) to assure that the ability to monitor level will not be interrupted.

However, if all level indication were to be lost during a loss of RGS inventory event, the operators would need to determine that .RPVRGS inventory loss was occurring by observing Table G-1 indicationssump and tank level changes. Surnp and tank level iRfGreasesTable G-1 RGS leakage indications must be evaluated against other potential sources of leakage such as cooling water sources inside the Gontainment to ensure they are indicative of RGS leakage. Visual observation of leakage from systems connected to the RGS in areas inside or outside the Gontainment that cannot be isolated could be indicative of a loss of RPV-RGS inventory.3

[The 15-minute duration for the loss of level indication was chosen because it is half of the EAL GS4-GS3.2_SITE AREA EMERGENGY E-AL-duration.

Significant fuel damage is not expected to occur until the core has been uncovered for greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per the analysis referenced in the EAL GG-1-GG3.2_basis.

Therefore this EAL meets the definition for an ALERT.]If RPV-RGS level leakage indications continues and RGS level cannot be monitored for 30 minutes or more, EAL G53.2 will reqiuire te-lower thenescalation to SITE AREA EMERGENGY-will e iaGS.ExplanationlDiscussion/Definitions:

Salem Page 2of 5 Rev. 0 (draft E)EAL#: CA3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 In this EAL, all RCS level indication is unavailable and the RCS inventory loss must be detected by the leakage indications listed in Table C-1. Level increases must be evaluated against other potential sources of leakage (SWS, Component Cooling Water, etc.) to ensure they are indicative of RCS leakage.In cold shutdown, the decay heat available to raise RCS temperature during a loss of inventory or heat removal event may be significantly greater than in the Refueling Mode. Entry into cold shutdown conditions may be attained within hours of operating at power or hours after refueling is completed.

Entry into the Refueling Mode procedurally may not occur for typically a few days or longer after the reactor has been shutdown.

Thus the heatup threat and therefore the threat to damaging the fuel clad may be lower for events that occur in the Refueling Mode with irradiated fuel in the Reactor Vessel (note that the heatup threat could be lower for cold shutdown conditions if the entry into cold shutdown was following a refueling).

Salem Page 3 of 5 Rev. 0 (draft E)EAL#: CA3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 Definitions:

UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CA1 Example EAL #2 2. SI (S2).OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System 3. UFSAR 5.6.5 Reactor Vessel Water Level 4. UFSAR 7.3.1.1.9 Instrumentation Used During a Loss of Coolant Accident 5. SI(S2).OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 6. S1(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System To >101 Foot Elevation 7. Reference drawing 208915-A-8823 Sh 1 8. UFSAR Figure 6.3-3 Containment Sump Pit 9. UFSAR 6.3.2.2 Equipment and Component Description (ECCS)10. UFSAR Figure 6.2-17 Containment Isolation Pressurizer Relief Tank Connections 11.S1(S2).OP-AB.RC-0001(Q)

Reactor Coolant System Leak Salem Page 4 of 5 Rev. 0 (draft E)EAL#: CA3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 This page intentionally blank Salem Page 5 of 5 Rev. 0 (draft E)EAL#: CA3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: C -Cold Shutdown / Refuel System Malfunction 3 -RCS Level Loss of RCS inventory affecting core decay heat removal capability 5 -Cold Shutdown, 6 -Refueling CS3.2 -SITE AREA EMERGENCY EAL: RCS level CANNOT be monitored for > 30 minutes with a loss of RCS inventory as indicated by ANY of the following (Note 3): " R44A> 5 R/hr* R10B > 3500 mR/hr" R2 > 104mRPhr" Erratic Source Range Monitor indication

ANY unexplained RCS leakage indication, Table C-1 Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Table C-1 RCS Leakage Indications" Rise in Containment sump pump run frequency" Aux Building sump level rise" PRT level rise" RWST level rise" RCDT level rise" Rise in RCS make-up rate" Observation of RCS leakage that is UNISOLABLE Salem Page 1 of 4 Rev. 0 (draft E)EAL#: CS3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 Basis: Under the conditions specified by this IGEAL, continued decrease in RCS/RPV level is indicative of a loss of inventory control. Inventory loss may be due to an RCS breach, pressure boundary leakage, or continued boiling in the RP-VReactor Vessel. Thus, declaration of a SITE AREA EMERGENCY is warranted.

Escalation to a GENERAL EMERGENCY is via EAL GG4CG3.2 or EAL RAG1.1.EAL H3 jIn the cold shutdown mode, normal RCS level -nd RPV level instrumentation systems will usually be available.

In the refueling mode, normal means of RPV-RCS level indication may not be available.

Redundant means of RP-VRCS level indication will usually be installed (including the ability to monitor level visually) to assure that the ability to monitor level will not be interrupted.

However, if all level indication were to be lost during a loss of RCS inventory event, the operators would need to determine that RP-V-RCS inventory loss was occurring by observing Table C-1 indications.

Table C-1 RCS leakage indicationssump and tank level c-s. Sump and tala must be evaluated against other potential sources of leakage such as cooling water sources inside the containment to ensure they are indicative of RCS leakage.]The 30-minute duration allows sufficient time for actions to be performed to recover inventory control equipment.

--wat-s- Vel ;i the RPV lo' Pes, thee ,-rate-above the Gcor Will increase.

The dose rate eto this; coreo shine should result in site specific, Monito indication and possible -alarm.-Thia E=AL Should consopýRVat~vi eatirnats a a4e ap-e c;f4G dOgFate stpoint 44d/ca tive of cOr-e r(, at T-AF). For B9WRs that do not ita"'d ..... M ,R.o~f inditein,.

re uc- vry4, Site ape ifi- I,'"l inrdiation, of corre unG,, ,r-y s.houId be fPost-TMI studies indicated that the installed nuclear instrumentation will operate erratically when the core is uncovered and that this should be used as a tool for making such determinations.]

Explanation/Discussion/Definitions:

This EAL applies to conditions in which the loss of decay heat removal capability has caused a significant drop in RCS water level below the bottom of the RCS hot leg penetration and core uncovery may be challenged.

RCS level indication capability does not support detection of RCS levels that low and, consequently, alternate means of assessing RCS inventory loss must be used: Salem Page 2 of 4 Rev. 0 (draft E)EAL#: CS3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226* As water level in the Reactor Vessel lowers, the dose rate above the core will increase.The dose rate due to this core shine should result in up-scaled general area low range containment monitor (1/2R10B & 1/2R2) and high range containment monitor (1/2R44A) indication and possible alarm. A dose rate setpoint indicative of core uncovery (i.e., level at top of active fuel) is a means to detect the onset of IMMINENT core damage. S-C-ZZ-MDC-2280 documents the basis for the threshold values for the R2, R1 OB and R44A values that indicate RCS level at or approaching the top of active fuel. Data from both Unit 1 and Unit 2 was reviewed and values rounded off to provide conservative threshold values that cover both Salem units based on how many fuel assemblies are in the Reactor Vessel and includes an appropriate reduction for radioactive decay of short lived radionuclides.

As Reactor Vessel level decreases life threatening levels could exist directly above the core; with water level at top of active fuel dose rates 20 feet above the core will be in excess of 38,000 R/hr. Additionally, post-TMI studies indicated that the installed nuclear instrumentation will operate erratically when the core is uncovered and that this should be used as a tool for making such determinations.

For EAL simplification, the thresholds are representative of a partially defueled core (80 fuel assemblies in the Reactor Vessel).* Erratic source range monitor indication may be identified by: o Source range count rate indicators N131 B and N132B o NIS Recorder NR45 o Audio count rate o SPDS o Process Computer* RCS inventory loss may be detected by the leakage indications listed in Table C-1.Level increases must be evaluated against other potential sources of leakage such as cooling water sources inside the Containment to ensure they are indicative of RCS leakage. Visual observation of leakage from systems connected to the RCS in areas inside or outside the Containment that cannot be isolated could be indicative of a loss of REACTOR VESSEL inventory.

Definitions:

UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.IMMINENT:

Mitigation actions have been ineffective, additional actions are not expectecd to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

Salem Page 3 of 4 Rev. 0 (draft E)EAL#: CS3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CS1 Example EAL #3 2. S-C-ZZ-MDC-2280, EAL Dose Rates to Radiation Detectors Following Loss of RPV Level during Refueling Operation 3. Technical Specifications 3.3.1.1 Reactor Trip System Instrumentation

4. UFSAR Table 7.5-2 Main Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operations

5. SC.IC-CC.NIS-0011(Q)

N31 Source Range 6. SC.IC-CC.NIS-0012(Q)

N32 Source Range 7. SI(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System to >101 Foot Elevation 8. UFSAR Figure 6.3-2 & 6.3-3 Containment Sump and Drain Trench & Containment Sump Pit 9. UFSAR 6.3.2.2 Equipment and Component Description (ECCS)10. UFSAR Figure 6.2-17 Containment Isolation Pressurizer Relief Tank Connections

11. S1 (S2).OP-AB.RC-0001 (Q) Reactor Coolant System Leak Salem Page 4 of 4 Rev. 0 (draft E)EAL#: CS3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Cold Shutdown / Refuel System Malfunction 3 -RCS Level Loss of RCS inventory affecting fuel clad integrity with Containment challenged 5 -Cold Shutdown, 6 -Refueling CG3.2 -GENERAL EMERGENCY RCS level CANNOT be monitored for _ 30 minutes with core uncovery indicated by ANY of the following (Note 3): " R44A> 5 RJhr" R1OB > 3500 mR/hr* R2 > 104 mR/hr* Erratic Source Range Monitor indication" ANY unexplained RCS leakage indication, Table C-1 AND ANY Containment Challenge indication, Table C-2 Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Salem Page 1 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 Table C-1 RCS Leakage Indications

Rise in Containment sump pump run frequency* Aux Building sump level rise* PRT level rise* RWST level rise* RCDT level rise* Rise in RCS make-up rate* Observation of RCS leakage that is UNISOLABLE Table C-2 Containment Challenge Indications

CONTAINMENT CLOSURE NOT established

Indications of > 4% H 2 inside Containment

UNPLANNED rise in Containment pressure Basis: This 4f-EAL represents the inability to restore and maintain RPV-RCS level to above the top of active fuel with containment challenged.

Fuel damage is probable if RPV-RCS level cannot be restored, as available decay heat will cause boiling, further reducing the RPV-RCS level. With the Ceontainment breached or challenged then the potential for unmonitored fission product release to the environment is high. This represents a direct path for radioactive inventory to be released to the environment.

This is consistent with the definition of a GENERAL EMERGENCY.

The GENERAL EMERGENCY is declared on the occurrence of the loss or IMMINENT loss of function of all three barriers.r i o Thr -Ai -c --ar Innn 'r,4 rnr, ,-v-nr',-'_r .r~c~4I, t2-j rr-. 1 ep#*r JQQ_ 7 1 pgo'~ rpf Qj-rQj4~0~~fA,1Jf ix-n Qa(' Qj-2R fl+/-2 1I1p2Z'Ithio1 txlSZ'iQ 4/ nrrI~Ior I e-IlA Q-I AIA~r /'n-. lot- c Al/ 10 Z'2,_ -AA0 I I 01,, 'IftIfI ý:*ý I A II e AF DPI IRIP,.Y (~r*y~, ~ ~* I~)~IP~VIPIVPI, i MI ~ -~ V o.-~ ~,,., V os-, ,-,*c. ;~, *-,,-, , i.-~ w-~ ~i~ .-..~-.....States, and. NUMARC 91 -06.

fo r ,,dustv AG. UPon to Assess fhn ..td.O man 'Me[t]A number of variables can have a significant impact on heat removal capability challenging the fuel clad barrier. Examples include: Salem Page 2 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226[BWAsJ] iRitial vessel level, shutd.ow heat removal system. design[fRW4G. mid-loop, reduced level/flange level, head in place, cavity flooded, RCS venting strategy, decay heat removal system design, vortexing pre-disposition, steam generator U-tube draining.Analysis indicates that core damage may occur within aras soon as one hour following continued core uncovery, therefore, 30 minutes was conservatively chosen.If CONTAINMENT CLOSURE is re-established prior to exceeding the 30 minute core uncovery time limit then escalation to GE would not occur.[Sit" 8hUtdown4 contingency planS 4p t oi ' pro vde for~ re stabshc.P:

g COQ1T/AIN44E-NI CLOSURE= folwing a loss of heat mp oF RCS inventory fU.. tio evut.]n[in the early stages of a Gore uGeve a event, it is ungwkete thot hydrogen buidup duc to a cm e YPG-en t aY-'rest in op eRCSleaikae.

m'I r- of i gasses in 'ita' '-"t. Howeyvtzt Containment monitoin hg and/,ormamplig shouRd be pelordmed to verifntrhis assumption onmd a usueral! be- aiabe.

ei. dgt' that ans epofi P--V-RS -e eisti.][For- bWvi, the USe of Seaonsdor-containment raeiation monitors should prouvde insdiotion o increased release that mayo be indicative of a cohalenge to secoidariy montaitoment.

The sit bpeoific radiotion moeiter vfales should be based on te Elos duraximum saofe va"RsC"'because these values ore easily rtecgnizable and have an emCSgienty basis.]E-AL4-#Table C-1 RCS leakage indicationsSump and tank level increases must be evaluated against other potential sources of leakage such as cooling water sources inside the CGontainment to ensure they are indicative of RCS leakage.fln the Cc-old Sshutdown mode, normal RCS level and RPV leve instrumentation systems will usually be available.

In the Rfefueling mode, normal means of RPV RCS level indication may not be available.

Redundant means of RPV RCSElevel indication will usually be installed (including the ability to monitor level visually) to assure that the ability to monitor level will not be interrupted.

However, if all level indication were to be lost during a loss of RCS inventory event, the operators would need to determine that RPV-RCS inventory loss was occurring by observing Table C-1 indications.

Table C-1 RCS leakage indicationssump and tank level changes. Sump and tank level inrfeases must be evaluated against other potential sources of leakage such as cooling water sources inside the Goontainment to ensure they are indicative of RCS leakage.4 As water level in the RPV lowers, the dose rate above the coeG Will increase.

The dose rat-[This E,4L shoul1d conseriatively estimpate a site specific dose rate Setpoint indicative of core uncOver-y 0ie., loeý! at TOAF). For BW4Rs that do not hove installed radiation monitors8 capable Salem Page 3 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 of i;dic-atin.g core UO..... , alt..ate Site &p......fic levl iH, ....o Of .............

shold be[Post-TMI studies indicated that the installed nuclear instrumentation will operate erratically when the core is uncovered and that this should be used as a tool for making such determinations.]

Explanation/Discussion/Definitions:

This EAL applies to conditions in which a significant drop in Reactor Vessel water level below the RCS hot leg penetration has occurred with prolonged core uncovery.

RCS level indication capability does not support detection of RCS levels that low and, consequently, alternate means of assessing RCS inventory loss must be used:* As water level in the Reactor Vessel lowers, the dose rate above the core will increase.The dose rate due to this core shine should result in up-scaled general area low range containment monitor (1/2R10B & 1/2R2) and high range containment monitor (1/2R44A) indication and possible alarm. A dose rate setpoint indicative of core uncovery (i.e., level at top of active fuel) is a means to detect the onset of IMMINENT core damage. S-C-ZZ-MDC-2280 documents the basis for the threshold values for the R2, R1 OB and R44A values that indicate RCS level at or approaching the top of active fuel. Data from both Unit 1 and Unit 2 was reviewed and values rounded off to provide conservative threshold values that cover both Salem units based on how many fuel assemblies are in the Reactor Vessel and includes an appropriate reduction for radioactive decay of short lived radionuclides.

As Reactor Vessel level decreases life threatening levels could exist directly above the core; with water level at top of active fuel dose rates 20 feet above the core will be in excess of 38,000 R/hr. Additionally, post-TMI studies indicated that the installed nuclear instrumentation will operate erratically when the core is uncovered and that this should be used as a tool for making such determinations.

For EAL simplification, the thresholds are representative of a partially defueled core (80 fuel assemblies in the Reactor Vessel).* Erratic source range monitor indication may be identified by: o Source range count rate indicators NI31B and N132B o NIS Recorder NR45 o Audio count rate o SPDS o Process Computer* RCS inventory loss may be detected by the leakage indications listed in Table C-1.Level increases must be evaluated against other potential sources of leakage such as Salem Page 4 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 cooling water sources inside the Containment to ensure they are indicative of RCS leakage. Visual observation of leakage from systems connected to the RCS in areas inside or outside the Containment that cannot be isolated could be indicative of a loss of RCS inventory.

Three conditions are associated with a challenge to Containment:

The status of CONTAINMENT CLOSURE indicates the ability to rely on the Containment as a barrier to fission product release." When hydrogen concentration in the Containment atmosphere exceeds 4%, the possibility of an explosive mixture exists inside Containment.

Elevated Containment atmosphere hydrogen concentration is alarmed at > 2% by overhead annunciator C-23, CNTMT H 2 LVL HI* An UNPLANNED rise in Containment pressure in the Cold Shutdown or Refueling Mode may signify an energy addition to the Containment such that the Containment cannot be relied upon as a barrier to fission product release.Definitions:

UNISOLABLE:

A breach or leak that cannot be promptly isolated from the Control Room.CONTAINMENT CLOSURE: Is the Salem procedurally defined action taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under existing plant conditions.

CONTAINMENT CLOSURE status is checked and verified using SI(S2).OP-AB.CONT-0001(Q).

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

EAL Basis Reference(s):

1. NEI 99-01, Rev. 05, CG1 Example EAL #2 2. OU-AA-103 Shutdown Safety Management Program 3. S1(S2).OP-AB.CONT-0001(Q)

Containment Closure 4. S-C-ZZ-MDC-2280, EAL Dose Rates to Radiation Detectors Following Loss of RPV Level during Refueling Operation 5. Technical Specifications 3.3.1.1 Reactor Trip System Instrumentation

6. UFSAR Table 7.5-2 Main Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operations Salem Page 5 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-226 7. SC.IC-CC.NIS-0011(Q)

N31 Source Range 8. SC.IC-CC.NIS-0012(Q)

N32 Source Range 9. SI(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System to >101 Foot Elevation 10. UFSAR Figure 6.3-2 & 6.3-3 Containment Sump and Drain Trench & Containment Sump Pit 11. UFSAR 6.3.2.2 Equipment and Component Description (ECCS)12. UFSAR Figure 6.2-17 Containment Isolation Pressurizer Relief Tank Connections

13. S1(S2).OP-AB.RC-0001(Q)

Reactor Coolant System Leak 14. 1(2)-EOP-FRCC-1 Response to Inadequate Core Cooling -Basis Document (pg 16)15. Salem EOP Setpoint Basis Document -Vendor Doc. #320832 16.SI(S2).OP-AR.ZZ-0003(Q)

OHA C-23, CNTMT H 2 LVL HI Salem Page 6 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-111-226 This page intentionally blank Salem Page 7 of 7 Rev. 0 (draft E)EAL#: CG3.2 SGS ECG -EAL Technical Bases EP-SC-1 11-227 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 4 -RCS Temperature UNPLANNED loss of decay heat removal capability with irradiated fuel in the Reactor Vessel 5 -Cold Shutdown, 6 -Refueling EAL# & Classification Level: CU4.1 -UNUSUAL EVENT EAL: An UNPLANNED Loss of Decay Heat Removal functions AND RCS Temperature has risen to > 200°F Basis: This WG-EAL is be-a precursor of more serious conditions and, as a result, is considered to be a potential degradation of the level of safety of the plant. In cold shutdown, the ability to remove decay heat relies primarily on forced cooling flow. Operation of the systems that provide this forced cooling may be jeopardized due to the unlikely loss of electrical power or RCS inventory.

Since the RCS usually remains intact in the Ceold Sshutdown mode a large inventory of water is available to keep the core covered.rvF,-,,~ inta an, -I4chut-,, Ir -nia, tin -,c' YY1.-I hQ nffminrf,~'

KAifhi, lint tr o nir e n mr-nf ý*

AtI I'JII A) A.'LALAI ~Y.VVJ[I##-11 "' "'J -4.. 4 fin L- .--pt~w,. LULL" d;;tu ;;@ ;;;uu', p' u wcuu;;;y ,'LUL tuuu; ;U!Lj; t' ,u ;' ;Uwt .blC peificor) 9 oeger r the reactor- has be en i"hutdo...

Thus the h.atup threat and thn th .at to. d .m ..in. the fuel c-1, -. -, I- 10K,=. fnrI P1. nhz t.IaL fh n c .Dý tho r.i fnlmi. raLnd 55511.11 1.5 .1. LI ILl II LAI.4t1.A 1.J LIRE LL4L tit.'L4ILA LA'L.' IL.A 511.11 IISI tIlLS! LA LJIILALL.4L 55, I F 1.11.51 ILAILI1..'I EL.! El 15 ILl Lfl ILl) 51 I I L..I LALSIL '.AEELALLALJ ISIS I'S LI LA I L.IEILI VS II I~f LA 1LA1LAX.SITI I~/. I

1.51.1-LSTLTLJVTJLTTS.A LSfJTLrLCWILlTCJV cur tA t w! i;;L .,:r Ff -rIredU F'U iV teUVlJ -- " I I ---- I During refueling, the level in the RPV-Reactor Vessel will normally be maintained above the Reactor Vessel RPV-flange.

Refueling evolutions that decrease water level below the Reactor Vessel RP--flange are carefully planned and procedurally controlled.

Loss of forced decay heat removal at reduced inventory may result in more rapid increases in RCS/RPV temperatures depending on the time since shutdown.P n nn; :rr hi I I" ' _ nnI nnt]If If-911I1]'--I.rfl..

01 ..indication may not be available iR the mode. Red-ulaa+nt me.ans of RPV level V V IV Salem Page 1 of 2 Rev. 0 (draft E)EAL#: CU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227 indication are thercforc procedurally installed to assure that the ability to mon~itorF leVel Will not be iRterrupted.

However, if all level and temperature indication.were......

to be 6ost i' either the cold shutdown of refucling moedes, EAL 2 w~u!d result in declaration o~f a NOUE if both tcmperaturc and levcl indicationR cannot be restored within 15 m~inutes from the loss of both ,means of indication.

Escalation to ALERT would be via EAL CA3.1 based on an inventory loss or EAL CA4.1 based on exceeding its temperature criteria.Explanation/Discussion/Definitions:

The Technical Specification cold shutdown temperature limit is 200 0 F.RCS coolant temperature may be indicated by the following instrumentation:

Core exit TCs (computer points T0031A, T0022A, T0046A, T001 4A)* Hot Leg temperatures (computer points T0419A, T0439A, T0459A, T0479A)* RHR HX inlet temperatures (computer points T0630A and T0631A) temperatue

RHR HX outlet temperatures (T0627A, T2360A)* RCS cold leg temperatures (T0406A, T0426A, T0446A, T0466A)Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CU4 Example EAL #1 2. SGS Technical Specifications Table 1.1, Operational Modes 3. 1(2)OP-AB.RHR-0001(Q)

Loss of RHR 4. 1(2)OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 5. SC.OP-DL.ZZ-0011(Q)

Reactor Coolant System Heatup/Cooldown Log Salem Page 2 of 2 Rev. 0 (draft E)EAL#: CU4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 4 -RCS Temperature UNPLANNED loss of decay heat removal capability with irradiated fuel in the Reactor Vessel 5 -Cold Shutdown, 6 -Refueling EAL# & Classification Level: CU4.2 -UNUSUAL EVENT EAL: An UNPLANNED Loss of Decay Heat Removal functions AND Loss of BOTH of the following: " All RCS Temperature indication

All RCS level indication AND> 15 minutes have elapsed (Note 3)Note 3: The Emergency Coordinator should NOT wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.Basis: This -G-EAL is be a precursor of more serious conditions and, as a result, is considered to be a potential degradation of the level of safety of the plant. In cold shutdown, the ability to remove decay heat relies primarily on forced cooling flow. Operation of the systems that provide this forced cooling may be jeopardized due to the unlikely loss of electrical power or RCS inventory.

Since the RCS usually remains intact in the Coold S-shutdown mode a large inventory of water is available to keep the core covered.co-d shuýt4dow

...d.t.os may be -tt-ined within heur.s of operaMtg-at power,.Etry, into the refueling mode pro.-edura, may not o.cur for- typica"y 100 ho.ur.s ('site&pe-GhF;.

c or- lengeF afte. the reactor- has beesutow.

Thus the h4eatup threat and ther, fo. -e TJJtI1't-4tf f- 4IIIA I II~I~ t*I-ep hi fIi IhymlTnrvnI r~m SI- -u nI fI m rLIni in fA- r-4I II II' i mLlit I I lI with-irraated f,'el :n th RPP (note tha thev hotu th.reat .... Ild be lower .br cold shutdow Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CU4.2 SGS ECG -EAL Technical Bases EP-SC-1 11-227 GGPditins if thea entr-)' into ood ShUtdoW9 was A~foGKowg a rcf~fucing.

In addition, the operator should be ablo to monitor: RCS t.mp.rature and RPV lev.. so that ÷Scalatio; to the a÷c" level vi GA 4 or CA1 Wig ..... ifreg'.....4 During refueling.

the level in the RPV-RCS will normally be maintained above the RPV Reactor Vessel flange. Refueling evolutions that decrease water level below the Reactor Vessel RPV-flange are carefully planned and procedurally controlled.

Loss of forced decay heat removal at reduced inventory may result in more rapid increases in RCSiRPV temperatures depending on the time since shutdown.[Un the cold shutdown mode,] nNormal means of Gere-RCS temperature indication and RCS level indication may not be available in the refueling mode. Redundant means of RPV RCS level indication are therefore procedurally installed to assure that the ability to monitor level will not be interrupted.

However, if all level and temperature indication were to be lost in either the _Ceold Sshutdown of Rrefueling modes, this EAL 2-would result in declaration of a NOUE if both temperature and level indication cannot be restored within 15 minutes from the loss of both means of indication.

Escalation to ALERT would be via EAL CA3.1 based on an inventory loss or EAL CA4.1 based on exceeding its temperature criteria.Explanation/Discussion/Definitions:

RCS water level is normally monitored using the instrument ranges in Attachment 2, page 10.During refueling, the reactor head and associated RVLIS piping are removed. Visual observation by personnel on the refuel floor in communication with the Control Room may also provide indication of refueling cavity water level and RCS water level.RCS coolant temperature may be indicated by the following instrumentation:

Core exit TCs (computer points T0031A, T0022A, T0046A, T001 4A)* Hot Leg temperatures (computer points T0419A, T0439A, T0459A, T0479A)" RHR HX inlet temperatures (computer points T0630A and T0631A) temperatue

RHR HX outlet temperatures (T0627A, T2360A)* RCS cold leg temperatures (T0406A, T0426A, T0446A, T0466A)Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CU4 Example EAL #2 2. Sl(S2).OP-SO.RC-0005(Q)

Draining the Reactor Coolant System to > 100 Foot Elevation 3. S1 (S2).OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System 4. UFSAR 5.6.5 Reactor Vessel Water Level Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CU4.2 SGS ECG -EAL Technical Bases EP-SC-111-227

5. UFSAR 7.3.1.1.9 Instrumentation Used During a Loss of Coolant Accident (LOCA)6. 1(2)OP-AB.RHR-0001(Q)

Loss of RHR 7. 1(2)OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 8. SC.OP-DL.ZZ-001 1(Q) Reactor Coolant System Heatup/Cooldown Log Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CU4.2 SGS ECG -EAL Technical Bases EP-SC-1 11-227 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Cold Shutdown / Refuel System Malfunction 4 -RCS Temperature Inability to maintain plant in cold shutdown 5 -Cold Shutdown, 6 -Refueling CA4.1 -ALERT An UNPLANNED event results in RCS temperature

> 200OF for > Table C-3 duration OR An UNPLANNED event results in RCS pressure increase > 10 psig due to a loss of RCS cooling (this portion of the EAL does NOT apply in Solid Plant conditions)

Table C-3 RCS Heatup Duration Thresholds RCS Integrity CONTAINMENT CLOSURE Duration Threshold Intact AND NOT in reduced NOT Applicable 60 minutes **inventory status NOT Intact OR Established 20 minutes **RCS is in a reduced inventory status NOT Established 0 minutes** IF a Decay Heat Removal System is placed in operation within the duration threshold and RCS Temperature is lowering, THEN this EAL is NOT Applicable Salem Page 1 of 5 Rev. 0 (draft E)EAL#: CA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227 Basis:EL= !AIlst Condition Tthe RCS Reheat-Heatup Duration Threshold table addresses complete loss of functions required for core cooling for greater than 60 minutes during RBFefueling and Ceold Sshutdown modes when RCS integrity is established.

{RCS integrity should be considered to be in place when the RCS pressure boundary is in its normal condition for the cold shutdown mode of operation (e.g., no freeze seals or nozzle dams). The status of CONTAINMENT CLOSURE in this condition is immaterial given that the RCS is providing a high pressure barrier to fission product release to the environment.]

The 60 minute time frame should allow sufficient time to restore cooling without there-being-a substantial degradation in plant safety.The RCS HeaturReheat Duration Threshold table also addresses the complete loss of functions required for core cooling for greater than 20 minutes during RE:efueling and Coold Sshutdown modes when CONTAINMENT CLOSURE is established but RCS integrity is not established or RCS inventory is reduced [(e.g., mid-loop operation in PWRs)]. /4s-d&abe'.. RCS ,teg÷,t,, shouId be ......., to be pýe4 When tR, CS .,F. ho ..4dary is in its nOrMal cOndition fo'r the col/d shutdownq mode of eperation (e.g., no freeze so ala or- noz dams).]The allowed 20 minute time frame was included to allow operator action to restore the heat removal function, if possible.

[The- llwe ti fraMP ,,s With the g-u,4idance pr..ided b, y Genei4, L 88_ 17, "ss .f Dec.y Hoa Removal" (d,4isussed late, , ba-sis*-1 and i-S believed to be conserA'ative given, that a low pr-essure Containment barner- to9 fission pr-oduct ,elas is establish~ed.

Finally, complete loss of functions required for core cooling during RErefueling and Ceold S-hutdown modes when neither CONTAINMENT CLOSURE nor RCS integrity are established.

fRCS integrity is in place when the RCS pressure boundary is in its normal condition for the cold shutdown mode of operation (e.g., no freeze seals or nozzle dams). No delay time is allowed because the evaporated reactor coolant that may be released into the Containment during this heatup condition could also be directly released to the environment.]

The note (**) in Table C-3 indicates that this EAL is not applicable if actions are successful in restoring an RGS-decayheat removal system to operation and RCS temperature is being reduced within the specified time frame.In EAL 2, t2nd Condition The 10 psig pressure increase addresses situations where, due to high decay heat loads, the time provided to restore temperature control, should be less than 60 minutes. The RCS pressure setpoint chosen should be 10 psig or the lowest pressure that the site can read on installed Control Board instrumentation that is equal to or greater than 10 psig.Escalation to SITE AREA EMERGENCY would be via EAL G91SEAL CS3.2 should boiling result in significant RPV-RCS level loss leading to core uncovery.Salem Page 2 of 5 Rev. 0 (draft E)EAL#: CA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227[For- P14Rs, tis 1Q and its associated EAL.. ar baS.d OR c.n.r.s .ai..sed by Genr-,o Letter 8 7, Loss of Decay Hcat Remoneval" A numbei of phenoendta such aS LERuaTn, Te sate g, s tu ofenerator U tube draining, Rxc level diffarben te wThni Specaing at acol loop conditiep, decayt heat rernova! system dovg, an fd utiol instrUMentation problems can load to .

heat ro ia 108t and oremino averty can ocurn. NR sh anadyS sho w that there art seqUednge that can cause cofre jucgvery en 15 to 20 minuthe and sever-e Gore damrage within an hour- after dccayheat remtval is lost.]A loss of Technical Specification components alone is not intended to constitute an ALERT.The same is true of a momentary unplanned excursion above the Technical Specification cold shutdown temperature limit when the heat removal function is available.

The EmcsgencY DirectohEmer2ency Coordinator must remain alert to events or conditions that lead to the conclusion that exceeding the EAL is IMMINENT.

If, in the judgment of the Emnergency DirecGtor Emrec oriao, an IMMINENT situation is at hand, the classification should be made as if the threshold has been exceeded.Explanation/DiscussionlDefinitions:

200'F is the Technical Specification cold shutdown temperature limit.10 psig is one-half of the 20 psig minor division on 1 (2)PI-403.

This instrument has a range of 0 to 600 psig. This RCS pressure indication is also displayed on SPDS Point U1(2)PT0403S and P250 Computer Point P0499A."Intact" is defined as all RCS penetrations between the core and Containment atmosphere are isolated, and a minimum of two RCS loops with U-tubes not drained and their associated Steam Generators are available as heat sinks for natural circulation. "Available as Heat Sinks" indicates each associated Steam Generator has a feed makeup source available, secondary water level is above the U-tubes, and a Steam Generator vent path exists.A "Reduced Inventory" condition exists when Reactor Vessel level is less than 101 ft.RCS coolant temperature may be indicated by the following instrumentation:

Core exit TCs (computer points T0031A, T0022A, T0046A, T0014A)* Hot Leg temperatures (computer points T0419A, T0439A, T0459A, T0479A)" RHR HX inlet temperatures (computer points T0630A and T0631A) terpepatur" RHR HX outlet temperatures (T0627A, T2360A)* RCS cold leg temperatures (T0406A, T0426A, T0446A, T0466A)Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.Salem Page 3 of 5 Rev. 0 (draft E)EAL#: CA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227 CONTAINMENT CLOSURE: Is the Salem procedurally defined action taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under existing plant conditions.

CONTAINMENT CLOSURE status is checked and verified using SI(S2).OP-AB.CONT-0001(Q).

IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

Salem Page 4 of 5 Rev. 0 (draft E)EAL#: CA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-227 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CA4 Example EAL #1 & #2 2. OU-AA-103 Shutdown Safety Management Program 3. SI(S2).OP-AB.CONT-0001(Q)

Containment Closure 4. SI(S2).OP-ST.CAN-0007(Q)

Refueling Operations

-Containment Closure 5. SGS Technical Specifications Table 1.1 Operational Modes 6. Sl(S2).IC-CC.RCP-0070(Q) 1(2)PT-403 Reactor Coolant System Hot Leg Pressure Channel II 7. SI(S2).OP-SO.RC-0005(Q)

Draining The Reactor Coolant System To >101 Foot Elevation 8. UFSAR 5.6.5 Reactor Vessel Water Level 9. S1(S2).OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System, Note pg 16 10.1 (2)OP-AB.RHR-0001 (Q) Loss of RHR 11. I(2)OP-AB.RHR-0002(Q)

Loss of RHR at Reduced Inventory 12. SC.OP-DL.ZZ-001 1(Q) Reactor Coolant System Heatup/Cooldown Log Salem Page 5 of 5 Rev. 0 (draft E)EAL#: CA4.1 SGS ECG -EAL Technical Bases EP-SC-1 11-228 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

EAL# & Classification Level: EAL: C -Cold Shutdown / Refuel System Malfunction 5 -Communications Loss of all onsite or offsite communications capabilities 5 -Cold Shutdown, 6 -Refueling, D -Defueled CU5.1 -UNUSUAL EVENT Loss of all Table C-4 Onsite communication methods affecting the ability to perform routine operations OR Loss of all Table C-4 Offsite communication methods affecting the ability to perform offsite notifications Table C-4 Communications Systems System Onsite Offsite Direct Inward Dial System (DID) X X Station Page System (Gaitronics)

X Station Radio System X Nuclear Emergency Telephone X System (NETS)Centrex Phone System (ESSX) X NRC (ENS) x Salem Page 1 of 4 Rev. 0 (draft E)EAL#: CU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-228 Basis: The purpose of this I-C-EAL and its associated EALs is to recognize a loss of communications capability that either defeats the plant operations staff ability to perform routine tasks necessary for plant operations or the ability to communicate issues with off-site authorities.

The loss of off-site communications ability is expected to be significantly more comprehensive than the condition addressed by 10 CFR 50.72.The availability of one method of ordinary off-site communications is sufficient to inform federal, state, and local authorities of plant issues. This EAL is intended to be used only when extraordinary means (e.g., relaying of information from radio transmissions, individuals being sent to off-site locations, etc.) are being utilized to make communications possible.Explanation/Discussion/Definitions:

Onsite and Offsite global communications include one or more of the systems listed in Table C-4.Direct Inward Dial System (DID)Direct Inward Dial (DID) system is named for the dominant feature of the commercial telephone service provided by the local telephone company for the site. DID allows station telephones to be extensions or tied lines of the same systems. These exchanges can take advantage of backup power supplies provided to the stations, and may use either PSEG microwave, commercial telephone system microwave, or buried cable transmission systems to maintain external communications.

This commercial telephone service is available as an additional backup for the NETS and Centrex/ESSX 1 system.Station Page System (Gaitronics)

Gaitronics is a completely transistorized voice communication system with five voice channels: one page and five party. The system is designed for use in extreme environmental conditions such as dust, moisture, heat and noise. The system consists of handsets, speakers and their associated amplifiers.

The power for this system is 120 volts AC from an inverted DC source to provide reliable communications during an emergency.

Station Radio System The Operations and Fire Protection Department UHF radio system is a multi-frequency system used routinely by both station Operations Departments and the Fire Protection Department.

When an emergency event is declared, these radio frequencies serve both station Operations Support Centers (OSC).Salem Page 2 of 4 Rev. 0 (draft E)EAL#: CU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-228 Nuclear Emergency Telephone System (NETS)The Nuclear Emergency Telecommunications System (NETS) is a privately controlled, self-contained telephone exchange that operates as a closed system, not accessible from other phone exchanges.

This feature allows the system to be dedicated to emergency response use. The system may use PSEG microwave, commercial telephone system microwave, fiber optics, or buried cable transmission as needed. The exchange switching equipment is maintained at the Environmental

& Energy Resource Center (EERC). As an independent system with an uninterruptible power supply, it may operate with or without local phone service or external power.Centrex Phone System (ESSX)The Centrex/Electronic Switch System Exchange 1(CentrexiESSX

1) is also a privately controlled exchange, which PSEG operates with its own microwave signal system. This system is also independent of local phone service, since each circuit is independently wired.The microwave signal is generated from corporate facilities in Newark, NJ, separated from any local effects of weather or telephone use. The exchange is accessible from other exchanges, but circuits are located only in PSEG facilities.

It is considered the primary backup for the NETS system.NRC (ENS)The Emergency Notification System (ENS) is a dedicated communications system with the NRC, which is part of the Federal Telecommunications System (FTS) and consists of direct lines to the NRC. FTS lines are used to provide general accident information.

These telephones are installed in the Control Room, TSC, and the EOF.This EAL is the cold condition equivalent of the hot condition EAL SU6.1.EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CU6 Example EAL #1 and 2 2. PSEG Nuclear Emergency Plan, Section 7 Communications

3. UFSAR 9.5.2 Communications System Salem Page 3 of 4 Rev. 0 (draft E)EAL#: CU5.1 SGS ECG -EAL Technical Bases EP-SC-1 11-228 This page intentionally blank Salem Page 4 of 4 Rev. 0 (draft E)EAL#: CU5.1 SGS ECG -EAL Technical Bases EP-SC-111-229 EAL Category: EAL Subcategory:

Initiating Condition:

Mode Applicability:

C -Cold Shutdown / Refuel System Malfunction 6 -Inadvertent Criticality Inadvertent Criticality 5 -Cold Shutdown, 6 -Refueling EAL# & Classification Level: CU6.1 -UNUSUAL EVENT EAL: UNPLANNED sustained positive startup rate observed on nuclear instrumentation Basis: This IC-EAL addresses criticality events that occur in Cold Shutdown or Refueling modes[(NUREG 1449, and Low Power .peraton Comm, ,e,,rcial Nu.lear Power P-laRtS in States)] such as fuel mis-loading events, and inadvertent dilution eVentS. This 4C EAL indicates a potential degradation of the level of safety of the plant, warranting a NOUE classification.

[TS cnonidition identified using period monitors/stadup rate monitor. The ten Tsustained" is ussee di order t o allow exclusion of expeeted shod termh pesrtter poenodsvstartup rates frm -planned fuel bundle or control ro'd movements during core alterationfo Tese sont tWrmp. These shortte oi er e taiup rates arc the reesut oftof thcicrase in neutronn populatioe due to subp a'tc Ima betideatified Escalation would be by Emergency DincatorNEmerency Coordinator Judgment.ExplanationlDiscussion/Defi nitions: The term "sustained" is used in order to allow exclusion of expected short term positive startup rates from planned fuel bundle or control rod movements during core alteration.

These short term positive startup rates are the result of the increase in neutron population due to subcritical multiplication.

Positive reactor startup rate may be identified by:* Source range startup rate indicators N131 D and N132D" NIS Recorder NR45* Audio count rate" SPDS* Process Computer Salem Page 1 of 3 Rev. 0 (draft E)EAL#: CU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-229 This EAL is the cold condition equivalent of the hot condition EAL SU3.1.Definitions:

UNPLANNED:

A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.Salem Page 2 of 3 Rev. 0 (draft E)EAL#: CU6.1 SGS ECG -EAL Technical Bases EP-SC-1 11-229 EAL Bases Reference(s):

1. NEI 99-01, Rev. 05, CU8 Example EAL #1 2. Technical Specifications 3.3.1.1 Reactor Trip System Instrumentation

3. UFSAR Table 7.5-2 Main Control Room Indicators

4. SC.IC-CC.NIS-0011(Q)

N31 Source Range 5. SC.IC-CC.NIS-0012(Q)

N32 Source Range Salem Page 3 of 3 Rev. 0 (draft E)EAL#: CU6.1 EAL Attachments (Support Materials)

SGS ECG -EAL Technical Bases EP-SC-1 11-230 Attachment 1 -Use of Fission Product Barrier Table Mode Applicability:

1 -Power Operations, 2 -Startup, 3 -Hot Standby, 4 -Hot Shutdown A point system is used to determine the Emergency Classification Level based on the Fission Product Barrier Table. Each Fission Product Barrier Loss and Potential Loss threshold is assigned a point value as noted below.Perform the following:

1. Review all columns of the Fission Product Barrier Table and identify which need further review.2. For each of the three barriers, determine the EAL with the highest point value. No more than one EAL should be selected for each barrier.3.4.Add the point values for the three barriers.Classify based on the point value sum as follows: If the sum ECG is: Classify as: EAL Att#UNUSUAL ANY loss or ANY potential EVENT loss of Containment I ANY loss or ANY potential 4, 5 ALERT loss of either Fuel Clad or 2 RCS Loss or potential loss of ANY two barriers 3 6-11 SITE AREA OR EMERGENCY Potential loss of 2 barriers with the loss of the 3rd barrier Loss of ANY two barriers GENERAL AND 4 EMERGENCY Loss or potential loss of third barrier Implement the appropriate ECG Attachment.

Continue to review the Fission Product Barrier Table for changes that could result in emergency escalation or de-escalation.

5.6.Salem Page 1 of 1 Rev. 0 (draft E)Attachment 1- Use of FPB Table SGS ECG -EAL Technical Bases EP-SC-1 11-231 Attachment 2 -EAL Basis Figures Figures referenced in the basis discussions of the EALs are listed in this Attachment.

Title AC Power Distribution CFST -Core Cooling CFST -Shutdown Margin CFST -Heat Sink CFST -Thermal Shock Thermal Shock Limit A Curve CFST -Containment Environment RCS Level Instrument Ranges Salem Page 1 of 10 Page No.2 4 5 6 7 8 9 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 AC Power Distribution The 500-kV switching station is connected to three 500-kV transmission lines. Two transmission lines go north to two major switching stations:

PSE&G New Freedom Switching Station and Atlantic City Electric's Orchard Switching Station. The New Freedom Switching Station is connected to the PSE&G 230-kV bulk power system via four 500/230-kV autotransformers.

Orchard Switching Station is also connected to Atlantic City Electric's 230-kV bulk power system via a 500/230-kV autotransformer.

In addition, it is connected to the Pennsylvania

/ New Jersey / Maryland 500-kV interconnected system. The third transmission line serves as a tie line to the adjacent Hope Creek 500-kV switchyard line which is also integrated into the Pennsylvania

/ New Jersey / Maryland 500-kV interconnected system.The 500-13 kV station power transformers are connected to different bus sections of the 500-kV switching station: " 13-kV north ring bus: Each 500-13 kV transformer T1 and T2 feeds two (one for each unit) 13-4 kV station power transformers T1 1, T21 and T1 2, T22 associated with group buses." 13kV south bus: Each 500-13kV transformer T3 and T4 respectively and feeds two (one for each unit) 13 4kV station power transformers T1 3, T24 and T1 4, T23 associated with vital buses and circulating water switchgear.

The 13-4kV station power transformers T13 and T14 (Unit 1) share the loads of three vital buses and two CW bus sections while T21 and T22 (Unit 2) share the loads of three vital buses and two CW bus sections.The onsite power sources for each unit consists of the main generator, the emergency diesel generators (one for each vital bus), and the Unit 3 40-MW gas turbine generator (one for both units). Any two EDGs and their associated vital buses can supply sufficient power for operation of the required safeguards equipment for a design basis LOCA coincident with a loss of offsite power. For the purposes of the EAL, availability of EDGs that have not been challenged to start during degradation of AC power sources to the 4KV vital buses should be based on meeting Technical Specification action requirements for loss of offsite AC power sources. The gas turbine generator can be manually started and paralleled with normal sources of plant startup or standby power but is normally used for peaking purposes.Procedure AB.LOOP-0001(Q) provides guidance to use the gas turbine to energize a 13KV ring bus during a blackout if necessary.

The gas turbine generator is not controlled by technical specifications, however, and for classification purposes under this EAL cannot be credited as a power source for the 4KV vital buses.Salem Page 2 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 AC Power Distribution (cont'd)DEARqS 5021 / 8 ~. 5021 DISC 1.5 HOPECREEK,_ZU L7~ ~ 22 i~ /500KVi RING 13US I'r _1, 2 -ý I SALEM 13KV'T60 LOAD DISCONNECT (FppurEci kiNG.BUS PROM GROLJWD FAULT)"T631 T/31"62 4KV GROUP 4KV GROUP 4KV VITAL 1ADD --14ASO [1ASO 14530 '6 13BS0 WI ~ 13 1 4CS D 13CD C 3E Tý13KV SOUTH BUS Salem Page 3 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 CFST -Core Cooling Salem Page 4 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 CFST -Shutdown Margin YEL rJ. :Etv rEL L 31 F Salem Page 5 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 CFST -Heat Sink YE L LN YELLOW#YELLOW YELLNY FFRHS3- FRHS-2 Salem Page 6 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11 -231 CFST -Thermal Shock Salem Page 7 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11 -231 Thermal Shock Limit A Curve 7 TS FLANT VERATI.-IEAL LIY] TS CHIRVE i2~uJ i~r If~UJ", tQ 1)D 2 O 2 1i 0 15ODf 12 ,, C S 2'iiii 3 0 1 TEV~ERATLRE

ýF&, .1~i Salem Page 8 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 CFST -Containment Environment LE--' THIO 79Fý5I4E Frr E-_, Salem Page 9 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-231 RCS Level Instrument Ranges CAVrTlY LJEýVEL 1I2*PZR COLO CAL MIDLOOP WIDE RANG3 LEVEL INDICATtOl SIGHT GLASS INDICATION 111'RVLIS REDUI:ED INVENTORY VtfttEI~ 7L.AM~E MIDLOOP NARROW RANGE LEVEL INDICATIONii 11ow%4-ii&Salem Page 10 of 10 Rev. 0 (draft E)Figures SGS ECG -EAL Technical Bases EP-SC-1 11-232 Attachment 3 -Definitions Selected words in the ECG Initialting Conditions (ICs) and Emergency Action Levels (EALs)have been set in all capital letters and bolded.These words are defined terms having specific meanings as they relate to this document and the definitions of these terms are provided below and in the basis for the EAL that the word is used in.AIRCRAFT:

Includes both small and large AIRCRAFT.

Examples of AIRCRAFT include general aviation Cessna, Piper and Lear type private planes, large passenger or freight planes as well as police, medical and media helicopters.

A large AIRCRAFT is referred to as an AIRLINER.AIRLINER/LARGE AIRCRAFT:

Any size or type of AIRCRAFT with the potential for causing significant damage to the plant (refer to the Security Contingency Plan for a more detailed definition).

BOMB: Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.

CIVIL DISTURBANCE:

A group of persons violently protesting station operations or activities at the site.CONFINEMENT BOUNDARY:

Is the barrier(s) between areas containing radioactive substances and the environment and includes the multi-purpose canister (MPC) and, for the purposes of this EAL, the associated cask shielding.

CONTAINMENT CLOSURE: Is the Salem procedurally defined action taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under existing plant conditions.

CONTAINMENT CLOSURE status is checked and verified using Sl(S2).OP-AB.CONT-0001(Q).

CREDIBLE / ACTUAL THREAT: Is a threat which poses a likely and serious danger to the safe operation of the facility or to site personnel and public safety.DEGRADED PERFORMANCE:

Assessment of degraded safe shutdown system performance includes examination of systems in standby status as well as those in operation.

When a safe shutdown system is in operation, its performance can be directly observed and compared to its design capability (e.g., rated flow is required but cannot be achieved).

When an operating safe shutdown system cannot fulfill its design function, its performance is degraded.

When a safe shutdown system is in standby, its performance capability may not be readily determined.

One or more of the following can provide indirect indication of its performance capability:

0 Electrical faults on power supplies Salem Page 1 of 4 Rev. 0 (draft E)Definitions SGS ECG -EAL Technical Bases EP-SC-1 11-232* Normally closed breakers in tripped position* System annunciators activated" System warning lights lit* Insufficient system pressure from keep-fill pumps* Elevated area temperatures or radiation levels* Increased sump pump operation in areas in which the system is located EXPLOSION:

A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

FAULTED: (PWRs) In a steam generator, the existence of secondary side leakage that results in an uncontrolled drop in steam generator pressure or the steam generator being completely depressurized.

FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.HOSTILE ACTION: An act toward Salem or Hope Creek or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate PSEG to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on Salem or Hope Creek. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the OCA).HOSTILE FORCE: One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.

IDENTIFIED LEAKAGE: As defined in T/S, shall be leakage (except Reactor Coolant Pump Seal Water Injection) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or, shall be leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or, shall be Reactor coolant system leakage through a steam generator to the secondary system (primary-to-secondary leakage).Salem Page 2 of 4 Rev. 0 (draft E)Definitions SGS ECG -EAL Technical Bases EP-SC-1 11-232 IMMINENT:

Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (unless a different time is specified).

INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI): A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.MALICIOUS ACT: Purposeful malevolent actions directed at compromising reactor safety and thus could directly or indirectly endanger the public health and safety.MINIMUM EXCLUSION AREA (MEA): The closest location just beyond the OWNER CONTROLLED AREA where a member of the general public could gain access. For Salem the MEA is 0.79 miles.NORMAL PLANT OPERATIONS:

Activities at the plant site associated with routine testing, maintenance, or equipment operations, in accordance with normal operating or administrative procedures.

Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from NORMAL PLANT OPERATIONS.

OWNER CONTROLLED AREA (OCA): Property owned, maintained and controlled by PSEG Nuclear as part of the Salem & Hope Creek Generating Station complex. For the purpose of emergency classification, area from the PSEG Nuclear access road checkpoint and inward towards the stations is considered the OCA.PRESSURE BOUNDARY LEAKAGE: As defined in T/S, shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.PROJECTILE:

An object that impacts Salem and/or Hope Creek that could cause concern for continued operability, reliability, or personnel safety.PROTECTED AREA (PA): A security controlled area within the OWNER-CONTROLLED AREA (OCA) that is enclosed by the security perimeter fence and monitored by intrusion detection systems. Access to the PA requires proper security clearance and is controlled at the Security Center.RUPTURED: (PWRs) In a steam generator, existence of primary-to-secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

SABOTAGE:

Deliberate damage, mis-alignment, or mis-operation of plant equipment with the intent to render the equipment inoperable.

Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision.

Salem Page 3 of 4 Rev. 0 (draft E)Definitions SGS ECG -EAL Technical Bases EP-SC-1 11-233 Attachment 4 -Glossary of Abbreviations

& Acronyms Acronyms and Abbreviations used in the ECG and ECG basis document are listed in this attachment.

AAAG -Accident Assessment Advisory Group (Delaware)

AB -Auxiliary Building AC -Alternating Current ADMSS -Administrative Support Supervisor

-TSC AFST -Auxiliary Feedwater Storage Tank AFW -Auxiliary Feedwater ALARA -As Low As Reasonably Achievable ARM -Area Radiation Monitor ASAP -As Soon As Possible ASM -Administrative Support Manager ATWT -Anticipated Transient Without Trip Aux -Auxiliary BKGD -Background BKR -Breaker (electrical circuit)BLDG -Building BNE -Bureau of Nuclear Engineering (NJDEPE)CAS -Central Alarm Station CCPM -Corrected Counts per Minute CEDE -Committed Effective Dose Equivalent CDE -Committed Dose Equivalent CET -Core Exit Thermocouple CFCU -Containment Fan Coil Unit CFR -Code of Federal Regulations CFST -Critical Safety Function Status Tree cIS -Containment Isolation System CM1 -Primary Communicator (CR)CM2 -Secondary Communicator (CR)CNTMT -Containment (Barrier)CoC -Certificate of Compliance CO 2 Carbon dioxide CP -Control Point CPM -Counts Per Minute CPS -Counts Per Second CR -Control Room CRS -Control Room Supervisor CREF -Control Room Emergency Filter System Salem Page 1 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-1 11-233 CVCS Chemical and Volume Control System DC DDE DEI DEMA DEP DHS DID DOE DOT DPCC/DCR DPM DPM DRCF EACS EAL EAS ECCS ECG EC EDG EDO EERC EMRAD ENC ENS EOC EOF EOP EPA EPA EPIP EPM EPZ ERDS ERF ERM ERO ESF ESSX FAA-Direct Current-Deep Dose Equivalent

-Dose Equivalent Iodine-Delaware Emergency Management Agency-Department of Environmental Protection (NJ)-Department of Homeland Security-Direct Inward Dial (phone system)-Department of Energy-Department of Transportation

-Discharge Prevention, Containment, & Countermeasures/Discharge Cleanup & Removal Plan-Decades per Minute-Disintegrations per Minute-Dose Rate Conversion Factor-Emergency Air Conditioning System (Control Room)-Emergency Action Level-Emergency Alert System (Broadcast)

-Emergency Core Cooling Systems-Event Classification Guide-Emergency Coordinator

-Emergency Diesel Generator-Emergency Duty Officer-Energy & Environmental Resource Center (Old NTC)-Emergency Radio (NJ)-Emergency News Center-Emergency Notification System (NRC)-Emergency Operations Center (NJ & DE)-Emergency Operations Facility-Emergency Operating Procedures

-Emergency Preparedness Advisor-Environmental Protection Agency-Emergency Plan Implementing Procedure-Emergency Preparedness Manager-Emergency Planning Zone (Plume EPZ = 10 Miles, Ingestion EPZ = 50 miles)-Emergency Response Data System-Emergency Response Facility-Emergency Response Manager-Emergency Response Organization

-Engineered Safety Feature-Electronic Switch System Exchange (Centrex) (Newark 973 Exchange phone system)-Federal Aviation Adm inistration Salem Page 2 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-11 11-233 FBI FC FFD FHB FPB FRCC FRCE FRCI FRERP FRHS FRSM FRTS FTS GE HCGS HEPA HP HVAC HX lAW IC ICMF IDLH IPEEE IR ISFSI I/S ISOL-Federal Bureau of Investigation

-Fuel Clad (Barrier)-Fitness For Duty-Fuel Handling Building-Fission Product Barrier-Functional Restoration Core Cooling-Functional Restoration Containment Environment

-Functional Restoration Coolant Inventory-Federal Radiological Emergency Response Plan-Functional Restoration Heat Sink-Functional Restoration Shutdown Margin-Functional Restoration Thermal Shock-Federal Telecommunications System (NRC)-General Emergency-Hope Creek Generating Station-High Efficiency Particulate Absorbers-Health Physics-Heating, Ventilation

& Air Conditioning

-Heat Exchanger-In Accordance With-Initiating Condition-Initial Contact Message Form-Immediately Dangerous to Life and Health-Individual Plant Examination of External Events-Intermediate Range-Independent Spent Fuel Storage Installation

-In Service-Isolation-Effective Neutron Multiplication Factor-Potassium Iodide-Kilovolt (1000 volts)-Lower Alloways Creek-Limiting Condition for Operation-Learning Development Center (aka -NAB or TB2)-Lens Dose Equivalent

-Lower Explosive Limit-Lower Flammability Limit-Lowest Level Detectable

-Loss of Coolant Accident-Loss of Offsite Power/ Loss of Offsite Power Accident Keff KI KV LAC LCO LDC LDE LEL LFL LLD LOCA LOP/LOPA Salem Page 3 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-111-233 LPZ MBD MDA MEA MEES MET MIDAS MIMS MOU MRO MSIV MSLI NAB NAWAS NCO NEI NEO NETS NFE NFPB NG NJSP NOAA NOSF NR NRC NSP NUMARC NWS OBE OCA ODCM OEM OHA OSB OSC PAG PAR PIM PMP PORV-Low Population Zone-Mixed Bed Demineralizer

-Minimum Detectable Amount-Minimum Exclusion Area (Salem = .79 miles, HC = .56 miles)-Major Equipment

& Electrical Status (Form)-Meteorological

-Meteorological Information Data Acquisition System-Metal Impact Monitoring System-Memorandum of Understanding

-Medical Review Officer-Main Steam Isolation Valve-Main Steam Line Isolation-Nuclear Administration Building (aka -LDC or TB2)-National Attack Warning Alert System-Nuclear Control Operator-Nuclear Energy Institute-Nuclear Equipment Operator-Nuclear Emergency Telecommunications System-Nuclear Fuels Engineer-Normal Full Power Background

-Noble Gas-New Jersey State Police-National Oceanographic and Atmospheric Administration

-Nuclear Operations Support Facility-Narrow Range-Nuclear Regulatory Commission

-Nuclear Site Protection

-Nuclear Management and Resources Council-National Weather Service-Operating Basis Earthquake

-Owner Controlled Area-Offsite Dose Calculation Manual-Office of Emergency Management

-Overhead Annunciators

-Operational Status Board (Form)-Operations Support Center-Protective Action Guideline-Protective Action Recommendation

-Public Information Manager-Pump-Power Operated Relief Valve Salem Page 4 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-1 11-233 PRT -Pressurizer Relief Tank PSEG -Public Service Enterprise Group PSIA -Pounds per Square Inch Absolute PSIG -Pounds Square Inch Gauge PWR -Pressurized Water Reactor PWST -Primary Water Storage Tank PZR -Pressurizer RAC -Radiological Assessment Coordinator RAD -Radiation RAL -Reportable Action Level RC -Reactor Coolant RCA -Radiologically Controlled Area RCAM -Repair and Corrective Action Mission RCDT -Reactor Coolant Drain Tank RCP -Reactor Coolant Pump RCS -Reactor Coolant System (Barrier)RHR -Residual Heat Removal RM -Recovery Manager RMO -Recovery Management Organization RMS -Radiation Monitoring System ROIC -Regional Operations

& Intelligence Center (NJSP)RPS -Radiation Protection Supervisor RPS -Reactor Protection System RRC -Remote Response Center (in NOSF)RSM -Radiological Support Manager RVLIS -Reactor Vessel Level Instrumentation System RWST -Refueling Water Storage Tank SAE -Site Area Emergency SAM -Severe Accident Management SAS -Secondary Alarm Station (Security)

SAT -Satisfactory SBO -Station Blackout SCBA -Self Contained Breathing Apparatus SCP -Security Contingency Procedure SDE -Shallow Dose Equivalent SDM -Shutdown Margin SFP -Spent Fuel Pool S/G -Steam Generator SGS -Salem Generating Station SGTR -Steam Generator Tube Rupture SI -Safety Injection SJAE -Steam Jet Air Ejector Salem Page 5 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-111-233 SM -Shift Manager SNM -Special Nuclear Material SOS -Systems Operations Supervisor (Security)

SPDS -Safety Parameter Display System SRPT -Shift Radiation Protection Technician SSCL -Station Status Checklist (form)SSE -Safe Shutdown Earthquake SSM -Site Support Manager SSNM -Strategic Special Nuclear Material STA -Shift Technical Advisor SUR -Start-up Rate T-COLD -Temperature Cold (Leg)T-HOT -Temperature Hot (Leg)TAF -Top of Active Fuel -BWR TDR -Technical Document Room TEDE -Total Effective Dose Equivalent TOAF -Top of Active Fuel -PWR TPARD -Total Protective Action Recommendation Dose T/S -Technical Specifications TSC -Technical Support Center TSS -Technical Support Supervisor TSTL -Technical Support Team Leader TSTM -Technical Support Team Member UE -Unusual Event UFSAR -Updated Final Safety Analysis Report UHS -Ultimate Heat Sink USCG -United States Coast Guard VCT -Volume Control Tank VDC -Volts Direct Current VLV -Valve WB -Whole Body WR -Wide Range Salem Page 6 of 6 Rev. 0 (draft E)Abbreviations

& Acronyms SGS ECG -EAL Technical Bases EP-SC-1 11-234 Attachment 5 -SGS-to-NEI 99-01 EAL Cross-Reference This cross-reference is provided to facilitate association and location of a Salem Generating Station EAL within the NEI 99-01 IC/EAL identification scheme. Further information regarding the development of the SGS EALs based on the NEI guidance can be found in the EAL Comparison Matrix.SGS NEI 99-01 EAL IC Example EAL RU1.1 AU1 1 RU1.2 AU1 1 RU1.3 AU1 3 RU2.1 AU2 1 RU2.2 AU2 2 RA1.1 AA1 1 RA1.2 AA1 1 RA1.3 AA1 3 RA2.1 AA2 2 RA2.2 AA2 1 RA3.1 AA3 1 RS1.1 AS1 1 RS1.2 AS1 2 RS1.3 AS1 4 RG1.1 AG1 1 RG1.2 AG1 2 RG1.3 AG1 4 CU1.1 CU3 1 CU2.1 CU7 1 CU3.1 Cui 1 CU3.2 CU2 2 Salem Page 1 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-1 11-234 SGS NEI 99-01 Example EAL ICEA EAL CU3.3 CU2 1 CU4.1 CU4 1 CU4.2 CU4 2 CU5.1 CU6 1,2 CU6.1 CU8 1 CAI. 1 CA3 1 CA3.1 CAI I CA3.2 CA1 2 CA4.1 CA4 1,2 CS3.2 CS1 3 CG3.2 CG1 2 EU1.1 E-HU1 1 HU1.1 HU1 1 HU1.2 HU1 2 HU1.3 HU1 4 HU1.4 HU1 3 HU1.5 HU1 5 HU2.1 HU2 1 HU2.2 HU2 2 HU3.1 HU3 1 HU3.2 HU3 2 HU4.1 HU4 1,2,3 HU6.1 HU5 1 HA1.1 HAl 1 HA1.2 HAl 2 HA1.3 HA1 4 HA1.4 HAl 3 HAl.6 HAI 5 Salem Page 2 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-1 11 -234 SGS NEI 99-01 EAL IC Example EAL HA2.1 HA2 1 HA2.2 HA2 1 HA3.1 HA3 1 HA4.1 HA4 1,2 HA5.1 HA5 I HA6.1 HA6 1 HS4.1 HS4 1 HS5.1 HS2 1 HS6.1 HS3 1 HG4.1 HG1 1,2 HG6.1 HG2 1 Sul.1 Sul 1 SU3.1 SU8 2 SU4.1 SU2 1 SU5.1 SU3 I SU6.1 SU6 1,2 SU7.1 SU4 1 SU7.2 SU4 2 SU8.1 SU5 1,2 SA1.1 SA5 1 SA3.1 SA2 I SA5.1 SA4 I SS1.1 SS1 1 SS2.1 SS3 1 SS3.1 SS2 I SS5.1 SS6 1 SG1.1 SG1 1 SG3.1 SG2 1 Salem Page 3 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-111-234 Fission Product Barrier EALs SGS NEI 99-01 EAL Barrier Threshold FB1-L FC Loss 1 FB4-L FC Loss 2 FB2-L FC Loss 3 FB3-L FC Loss 6 FB5-L FC Loss 8 FB1-P FC P-Loss 1 FB2-P FC P-Loss 1 FB3-P FC P-Loss 3 FB4-P FC P-Loss 4 FB5-P FC P-Loss 8 RB2-L RCS Loss 2 RB3-L RCS Loss 4 RB1-L RCS Loss 6 RB4-L RCS Loss 8 RB1-P RCS P-Loss 1 RB2-P RCS P-Loss 1 RB3-P RCS P-Loss 2 RB4-P RCS P-Loss 8 CB1-L CNTMT Loss 2 CB2-L CNTMT Loss 2 CB3-L CNTMT Loss 4 CB4-L CNTMT Loss 4 CB5-L CNTMT Loss 5 CB6-L CNTMT Loss 8 CB1-P CNTMT P-Loss 1 CB6-P CNTMT P-Loss 2 CB7-P CNTMT P-Loss 2 Salem Page 4 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-1 11-234 SGS NEI 99-01 EAL Barrier Threshold CB8-P CNTMT P-Loss 2 CB3-P CNTMT P-Loss 3 CB4-P CNTMT P-Loss 3 CB5-P CNTMT P-Loss 6 CB2-P CNTMT P-Loss 7 CB9-P CNTMT P-Loss 8 Salem Page 5 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-111-234 This page intentionally blank Salem Page 6 of 6 Rev. 0 (draft E)Cross-Reference SGS ECG -EAL Technical Bases EP-SC-l 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Purpose: This is a reference document that contains the methodology and calculations used in developing the thresholds for radiological release based Emergency Action Levels (EALs). The radiological EALs covered under this document are based on EALs AUl, AA1, AS I and AGI in NEI-99-01, Rev. 05, "Methodology for Development of Emergency Action Levels".Reference Materials:

NEI 99-01, Rev. 05 -Methodology for Development of Emergency Action Levels, EALs AU 1, AA1, ASI and AGI* NEI 99-01, Rev. 05 -Appendix A: Basis for Radiological Effluent EALs* Salem ODCM Rev. 24* EPA 400-R-92-00 1, Manual or Protective Action Guides and Protective Actions for Nuclear Incidents Terms & Calculation Constants and origin:* ODCM -Offsite Dose Calculation Manual" Hours in one year: 365.25 days X 24 hrs/day = 8766 hour0.101 days 2.435 hours 0.0145 weeks 0.00334 months s* EDE -Effective Dose Equivalent

CDE -Committed Dose Equivalent

CEDE -Committed Effective Dose Equivalent

= CDE X Weighting Factor (thyroid per 1OCFR2O)* TEDE -Total Effective Dose Equivalent

= EDE + CEDE* PAG -Protective Action Guideline:

Per EPA = 1 000mRem TEDE dose or 5000 mRem thyroid dose.Actual or projected values above these guidelines will require offsite protective actions to be implemented.

ODCM Rad Effluent Limit -500 mReli/year is a total site Noble Gas limit that includes Salem 1, Salem 2 and Hope Creek. Therefore, Salem will have an administratively controlled limit of 1/2 the total site limit or 250 mRemn/year for EAL calculation purposes.* Allocation Factor (AF) = .5 -As defined in the Salem ODCM, (page 83) this is an administrative control imposed to ensure that the combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limit from the site. The Site AF is only used in the UE and Alert EALs.Salem Page 1 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs" X/Q = Site Specific Atmospheric dispersion to the site boundary.

Ul and U2 Value = 2.2E-06 sec/n 3.Origin -Salem ODCM, Rev. 24, Table 2-2.1 and 2-2.2, Parameters for Gaseous Alarm Setpoint Determinations.

DRCF = Site Specific Dose Rate Conversion Factor. Ul and U2 Value = 4.7E+02 mnrem/year per uCi/in 3.Origin -Salem ODCM, Rev. 24, Table C-i, Effective Dose Factors, Noble Gases -Total Body and Skin -Total Body Effective Dose Factor.Index: (Radiological Release EAL Calculations)

Salem EALS: Page #: Unusual Event EAL AU 1.1 -(Default Release Rate EAL) 4 Unusual Event EAL AU1.2 -(2 time alarm) No Calc needed Unusual Event EAL AU 1.3 -(Sample Analysis Concentration) 5 Unusual Event EAL AU 1.4 -(Perimeter Monitoring System -NA)Unusual Event EAL AU 1.5 -(Dose Assessment

-NA)Alert EAL AA1.1 -(Default Release Rate EAL) 6 Alert EAL AA1.2 -(200 time alarm) No Calc needed Alert EAL AA1.3 -(Sample Analysis Concentration) 7 Alert EAL AA1 .4- (Perimeter Monitoring System -NA)Alert EAL AA1.5 -(Dose Assessment-NA)Site Area Emergency EAL AS 1.1 -(Default Release Rate EAL) 8 Site Area Emergency EAL AS 1.2 -(Dose Assessment) 9 Site Area Emergency EAL AS 1.3 -(Perimeter Monitoring Sys -NA)Site Area Emergency EAL AS 1.4 -(PA boundary dose rate) 10 Site Area Emergency EAL AS1.4 -(1-131 Field Survey Sample Analysis) 11 General Emergency EAL AG 1.1 -(Default Release Rate EAL) 12 General Emergency EAL AG1.2 -(Dose Assessment) 13 General Emergency EAL AG1.3 -(Perimeter Monitoring Sys -NA)General Emergency EAL AG1 .4- (PA boundary dose rate) 14 General Emergency EAL AG1.4 -(1-131 Field Survey Sample Analysis) 15 Salem Page 2 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Submitted By: Craig Banner Date: 12-15-2009 EP Review By: Gary Youn Date: 12-17-2009 Teclmical Review: Jenny Shelton Date: 06-04-2010 Salem SFAM Review: Phil Quick Date: 06-07-2010 HC SFAM Review: Johm Molner Date: 06-04-2010 Date: 06-09-2010 CFAM Approval:

David Burgin Salem Page 3 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-l 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: Unusual Event EAL AU1.1 -(Default Release Rate EAL)Objective of Calculation:

Provide a Salem Radiological Release Rate value that equates to a Release that is > 2 times the ODCM limit of 500 lnRelryear.

Discussion:

The ODCM limit of 500 mRerl/year is a total site limit that includes Salem 1, Salem 2 and Hope Creek.Therefore, Salem 1 &2 will have an administratively controlled limit of 1/2 the total site limit or 250 mRem/year for EAL calculation purposes.This EAL does not include Iodine Release Rates, since the Plant Vent does not have an Iodine detector.Release Rate = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) which would result in a TEDE Dose Rate of 250 mRem/year, The EAL value will be 2 times this release rate.Derivation

/ Calculation:

Radiological ODCM Limit Calculation for Noble Gas: Release Rate (uCi/Sec)

= ODCMLinmit(m Re m / year) * (SiteAllocationFactor)(ODCMX /Q) * (ODCMDRCF)

ODCM Limit = 500 mRem/Year Salem ODCM X/Q = 2.20E-06 sec/mi 3 Salem ODCM DRCF = 4.70E+02 mRelr/yr/uCi/m 3 Site Allocation Factor = 5.00E-01 Release Rate (uCi/Sec)

= (500m Rei m/yr) * (5.OOE -01)(2.20E -06sec/ in 3) * (4.70E + 027n Re i / yri / PCi / n 3 7)Release Rate = 2.42E+05 uCi/Sec (Also the ODCM Limit Release Rate Value)EAL Value = 2 times the Release Rate UE EAL Value: (EAL # RUI.1)Total (S1 & S2) Noble Gas Release Rate > 4.84E+05 pCi/sec Salem Page 4 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-I 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: Unusual Event EAL AU1.3 -(Sample Analysis Concentration)

Objective of Calculation:

Provide a Radiological Release Noble Gas and Iodine Sample Concentration that equates to a Release that is> 2 times the ODCM limit of 500 mRem/year.

Discussion:

The ODCM limit of 500 mRem/year (Noble Gas/Total Body) and 1500mRero/year (1-13 1/Child Thyroid) is a total site limit that includes Salem 1, Salem 2 and Hope Creek. Therefore, Salem 1&2 will have an administratively controlled limit (allocation factor) of V2 the total site limit or 250 mRem/year (Noble Gas/Total Body) and 750 mRelrdyear (1-13 1/Child Thyroid) for EAL calculation purposes.

This allocation factor is used in the calculation that derived the Noble Gas and Iodine release rates.Derivation

/ Calculation:

Calculation of the threshold sample concentrations are as follows: Formula: Concentration (uCi/cc) = Single Unit Re leaseRate

2 ConversionFactor

VentFlowRate Noble Gas Sample Concentration

= 1.2=E+05kCi/se*2 6.4E-03 tCi/cc 472x8OOOOcfn7

10. 5E + O0 pCi / see* 2 1-131 Saple Concentration

= -= 5.6E-07 [tCi/cc 472x80000cfin Where:* Single Unit (Ul or U2) Release Rate (Noble Gas) = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) as derived for EAL AU 1.1 split between Unit 1 and 2 (divided by 2) -2.42E+05 uCi/Sec/2

= 1.21E+05 uCi/Sec per Unit.o Single Unit (UI or U2) Release Rate (Thyroid/I-131)

= 10.5 uCi/Sec per unit as per ODCM, Rev.24, Section 2.3.2 o 2 = EAL criteria of 2X ODCM value* 472 = conversion factor (28,317 cc/ft 3 x 1 min/60 sec)o 80000 cfih = Plant Vent Flow (nonrnal)UE EAL Values: (EAL# RU1.3)Noble Gas Sample Concentration

> 6.4E-03 ýtCi/cc 1-131 Sample Concentration

> 5.6E-07 pCi/cc Salem Page 5 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC- 111-23 5 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: ALERT EAL AA1.1 -(Default Release Rate EAL)Objective of Calculation:

Provide a Radiological Release Rate value that equates to a Release that is > 200 times the ODCM limit of 500 mRem/year.

Discussion:

The ODCM limit of 500 mRerl/year is a total site limit that includes Salem 1, Salem 2 and Hope Creek.Therefore, Salem 1 &2 will have an administratively controlled limit of 1/2 the total site limit or 250 mRem!year for EAL calculation purposes.This EAL does not include Iodine Release Rates, since the Plant Vent does not have an Iodine detector.Release Rate = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) which would result in a TEDE Dose Rate of 250 mRear/year.

The EAL Value will be > 200 times the release rate.Derivation

/ Calculation:

ODCM Limit Calculation for Noble Gas: Release Rate (uCi/Sec)

= (ODCMLimit -m Re mi / year) * (SiteAllocationFactor)(ODCMX / Q) * (ODCMDRCF)

ODCM Limit = 500 mRem!Year Salem ODCM X/Q = 2.20E-06 sec/m3 Salem ODCM DRCF = 4.70E+02 mRemlyr/uCi/m 3 Site Allocation Factor = 5.OOE-01 Release Rate (uCi/Sec)

= (500m Re m /yr) * (5.OOE -01)(2.20E -06sec/ in 3) * (4.70E + 027 Re M / yr / PCi / 7n 3)Release Rate = 2.42E+05 uCi/Sec EAL Value = > 200 times the Release Rate Alert EAL Value: (EAL# RAI.1)Total (Si & S2) Noble Gas Release Rate > 4.84E+07 gCi/sec Salem Page 6 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: ALERT EAL AA1.3 -(Sample Analysis Concentration)

Obiective of Calculation:

Provide a Radiological Release Noble Gas and Iodine Sample Concentration that equates to a Release that is> 200 times the ODCM limit of 500 tnRem/year.

Discussion:

The ODCM limit of 500 mRem/year (Noble Gas/Total Body) and 1500tmRer/year (1-13 l/Child Thyroid) is a total site limit that includes Salem 1, Salem 2 and Hope Creek. Therefore, Salem 1&2 will have an administratively controlled limit (allocation factor) of V2 the total site limit or 250 mRem/year (Noble Gas/Total Body) and 750 mRemr/year (1-13 1/Child Thyroid) for EAL calculation purposes.

This allocation factor is used in the calculation that derived the Noble Gas and Iodine release rates.Derivation

/ Calculation:

Calculation of the threshold sample concentrations are as follows: Fonrmula:

Concentration (uCi/cc) SingleUnit ReleaseRate

200 ConversionFactor

VentFlowRate 1.21IE + 05/,uCi /see* 200 Noble Gas Sample Concentration

= -.21E OOfi 2 = 6.4E-01 gCi/cc 472x80000cfm 1 0.5E + O0/jiCi / sec* 200 1-131 Sample Concentration

= = 5.6E-05 gCi/cc 472x80000cfmn Where:* Single Unit (Ul or U2) Release Rate (Noble Gas) = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) as derived for EAL AU 1.1 split between Unit 1 and 2 (divided by 2) =2.42E+05 uCi/Sec/2

= 1.21E+05 uCi/Sec per Unit.* Single Unit (UI and U2) Release Rate (Thyroid/I-131)

= 10.5 uCi/Sec per unit as per ODCM, Rev. 24, Section 2.3.2* 200 = EAL criteria of> 200X ODCM value* 472 = conversion factor (28,317 cc/ft 3 x 1 min!60 sec)* 80000 cfrn = Plant Vent Flow (normal)Alert EAL Values: (EAL# RA1.3)Noble Gas Sample Concentration

> 6.4E-01 1Ci/cc 1-131 Sample Concentration

> 5.6E-05 pCi/cc Salem Page 7 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC- I 11 -23 5 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: SITE AREA EMERGENCY

-EAL AS1.1 -(Default Release Rate EAL)Objective of Calculation:

Provide a Radiological Release Rate value that equates to a Release resulting in an offsite dose of > 100 mrem EDE at or beyond the site boundary.Discussion:

This IC addresses radioactivity releases that result in doses at or beyond the site boundary that exceed 10%of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.The monitor reading EALs should be determined using a dose assessment method that back calculates from the dose values specified in the IC. Since doses are generally not monitored in real-time, it is suggested that a release duration of one hour be assumed, and that the EALs be based on a site specific boundary (or beyond)dose of >100 rnrem whole body. Iodine Release Rates for this EAL are excluded since the Plant Vent Radiation Monitoring System does not include an Iodine detector.The meteorology and source term used are the same as used for determining AUl and AA1 monitor reading EALs.Release Rate = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) which would result in a EDE Dose Rate of> 100ImRem/hr at the site boundary or beyond.Derivation

/ Calculation:

Radiological Limit Calculation for Noble Gas: Release Rate (uCi/Sec)

= (1 0%ofPAG)m Re m(accumulatedinlhour)(ODCMX / Q) * (ODCMDRCF) 10% of PAG = 100 mRem dose accumulated in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Salem ODCM X/Q = 2.20E-06 sec/m3 Salem ODCM DRCF = 5.36E-02 mRem/hr/uCi/m 3 (4.70E+02 mRemlyr/uCi/m 3 / 8766 hrs/yr)Site Allocation Factor = not used for SAE and GE EALs Release Rate (uCi/Sec)

= 1 00m Re ni(doseaccuinulatedinlhr)

(2.20E -06sec/m 3 ) * (5.36E -02m Re mn / hr / pCi /m 3)SAE EAL Value: (EAL# RSJ.1)Total (Si & S2) Noble Gas Release Rate > 8.48E+08 uCi/Sec Salem Page 8 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: SITE AREA EMERGENCY

-EAL AS1.2 -(Dose Assessment)

Objective of Calculation:

Using actual meteorology, provide a dose assessment SSCL threshold TEDE 4-Day Dose value that is equivalent to a TEDE dose of >100 mRem and a Thyroid-CDE Dose of 500 mRem.Discussion:

This IC addresses radioactivity releases that result in doses at or beyond the site boundary that exceed 10%of the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and involve fuel damage.Derivation

/ Calculation:

The dose assessment output on the SSCL is reported at varying distances from the plant as a TEDE 4-Day dose. This TEDE 4-day dose assumes a 4 hr release duration.

To obtain the approximate dose for a projected release condition of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the TEDE 4-day dose value would need to be divided by 4.A TEDE 4-Day Dose > 4.OE+02 mRem correspond directly to an EDE dose rate value of 100 mRem/hr and exceeds 10% of the EPA Protective Actions Guides (PAGs). The Thyroid-CDE Dose > 2.0E+03 mRem correspond directly to an CDE dose rate value of 500 mRem/hr and exceeds 10% of the EPA Protective Actions Guides (PAGs) which was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE..Dose Assessment using actual meteorological data provides an accurate indication of release magnitude.

The use of dose assessment based EALs is therefore preferred over the use of Release Rate based EALs which utilize calculations which have built-in inaccuracies because ODCM default Meteorological data is used.SAE EALs Values: (EAL# RS1.2)Dose Assessment TEDE 4-Day Dose > 4.OE+02 mRem Dose Assessment CDE Dose > 2.OE+03 mRem -based on Dose Assessment using Plant Vent effluent isotopic sample analysis as input to MIDAS and NOT based on a default Noble Gas to Iodine Ratio Salem Page 9 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-l 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: SITE AREA EMERGENCY

-EAL AS1.4 -(PA boundary dose rate)Objective of Calculation: ,I .......Provide a PROTECTED AREA Boundary dose rate that equates to an offsite dose of> 100 mRem EDE.Discussion:

This IC addresses radioactivity releases that result in field survey results (closed window) dose rates greater than 100 mR/hr expected to continue for 60 minutes or longer at or beyond the site boundary.

This value exceeds 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.Derivation

/ Calculation:

A Field Measured Dose Rate of> 1.0E+02 mReemihr corresponds directly to a dose values that exceed 10%of the EPA Protective Actions Guides (PAGs).SAE EAL Value: (EAL# RS1.3)Dose Rate > 100 mRem/hr Salem Page 10 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-I 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: SITE AREA EMERGENCY

-EAL AS1.4 -(1-131 Field Survey Sample Analysis)Objective of Calculation:

Provide a Field Survey Sample Analysis value that equates to an offsite release that would result in a dose of> 500 mRem Thyroid CDE at or beyond the PROTECTED AREA Boundary.Discussion:

This EAL addresses a radioactivity release field survey 1-131 sample concentration or count rate that would result in a Thyroid CDE dose of greater than 500 mRem for one hour of inhalation at or beyond the site boundary.

This value exceeds 10% of the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.The Iodine-131 field survey sample concentration and count rate threshold is based on 1-131 dose conversion factors (DCFs) from EPA-400. The thresholds are based on a Thyroid-CDE Dose Rate of> 500 mRem/hr for 1-131.Field Survey 1-131 Sample Analysis results are provided as a sample concentration in units of uCi/cc for field samples counted in a Multi-Channel-Analyzer (MCA).Derivation

/ Calculation:

The release sample concentration calculations are as follows.The sample concentration is calculated using the 1-131 Dose Conversion Factor from EPA-400: Solving the following equation for ptCi/cc: mRem/hr = (jiCi/cc)(Dose Conversion Factor)Then;1-131 Sample Concentration

(ýtCi/cc)

= ( ) / 3.85E-07 (etCi/c/1.30E + 09mtRem / pCi / cc / hr Where 1.30E+09 mRelr4pCi/cc/hr is the Dose Conversion Factor from EPA-400, Table 5-4, Thyroid Dose, and includes the EPA breathing rate.SAE EAL Values: (EAL# RS1.3)1-131 Concentration

> 3.85E-07 gCi/cc Salem Page 11 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-l 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: GENERAL EMERGENCY

-EAL AGI.1 -(Default Release Rate EAL)Objective of Calculation:

Provide a Radiological Release Rate value that equates to a Release resulting in an offsite dose of> 1000 mrem EDE at or beyond the site boundary.Discussion:

This IC addresses radioactivity releases that result in doses at or beyond the site boundary that exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and likely involve fuel damage.The monitor reading EALs should be determined using a dose assessment method that back calculates from the dose values specified in the IC. Since doses are generally not monitored in real-time, it is suggested that a release duration of one hour be assumed, and that the EALs be based on a site specific boundary (or beyond)dose of > 1000 1Trem whole body. Iodine Release Rates for this EAL are excluded since the Plant Vent Radiation Monitoring System does not include an Iodine detector.The meteorology and source ternn used are the same as used for determining AU1 and AA1 monitor reading EALs.Release Rate = Total Noble Gas Release Rate from Salem (Unit 1 & Unit 2) which would result in a TEDE Dose Rate of> 1000 mRem/hr at the site boundary or beyond.Derivation

/ Calculation:

Radiological Effluent Technical Specifications/ODCM Limit Calculation for Noble Gas: Release Rate (uCi/Sec)

= I00%PAG(m Re in)Accumulatedinlhr (ODCMX / Q) * (ODCMDRCF) 100% of PAG = 1000 mRem accumulated in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Salem ODCM X/Q = 2.20E-06 sec/in 3 Salem ODCM DRCF = 5.36E-02 mRemrnhr/uCi/m 3 (4.70E+02 rnRemlryr/uCi/m 3 / 8766 hrs/yr)Site Allocation Factor -not used for SAE and GE EALs Release Rate (uCi/Sec) 10007m Re m(doseaccumulatedinlhr)

(2.20E -06sec/m 3 ) * (5.36E -02m Re m / hr / pCi / 7n 3)GE EAL Value: (EAL# RGJ.1)Total (S1 & S2) Noble Gas Release Rate > 8.48E+09 uCi/Sec Salem Page 12 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: GENERAL EMERGENCY

-EAL AG1.2 -(Dose Assessment)

Objective of Calculation:

Using actual meteorology, provide a dose assessment SSCL threshold TEDE 4-Day Dose value that is equivalent to a TEDE dose of> 1000 mRem and a Thyroid-CDE Dose of> 5000 toRem.Discussion:

This IC addresses radioactivity releases that result in doses at or beyond the site boundary that exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and involve fuel damage.Derivation

/ Calculation:

The dose assessment output on the SSCL is reported at varying distances firom the plant as a TEDE 4-Day dose. This TEDE 4-day dose assumes a 4 hr release duration.

To obtain the approximate dose for a projected release condition of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the TEDE 4-day dose value would need to be divided by 4.A TEDE 4-Day Dose > 4.OE+03 mRem correspond directly to an EDE dose rate value of >1000 mRem/hr and exceeds the EPA Protective Actions Guides (PAGs). The Thyroid-CDE Dose > 2.OE+04 mRem correspond directly to an CDE dose rate value of> 5000 mReml/hr and exceeds the EPA Protective Actions Guides (PAGs) which was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE..Dose Assessment using actual meteorological data provides an accurate indication of release magnitude.

The use of dose assessment based EALs is therefore preferred over the use of Release Rate based EALs which utilize calculations which have built-in inaccuracies because ODCM default Meteorological data is used.GE EAL Values: (EAL# RGJ.2)Dose Assessment TEDE 4-Day Dose > 4.OE+03 mRem Dose Assessment CDE Dose > 2.OE+04 mRem -based on Dose Assessment using Plant Vent effluent isotopic sample analysis as input to MIDAS and NOT based on a default Noble Gas to Iodine Ratio Salem Page 13 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Technical Bases EP-SC-111-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: GENERAL EMERGENCY

-EAL AG1.4 -(PA boundary dose rate)Objective of Calculation:

Provide a PROTECTED AREA Boundary dose rate that equates to an offsite dose of> 1000 mRem EDE.Discussion:

This IC addresses radioactivity releases that result in doses at or beyond the site boundary that exceed the EPA Protective Action Guides (PAGs). Public protective actions will be necessary.

Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public and involves fuel damage.Derivation

/ Calculation:

A Field Measured Dose Rate of> 1.OE+03 mRem/hr corresponds directly to a dose values that exceed the EPA Protective Actions Guides (PAGs).GE EAL Value: (EAL# RG1.3)Dose Rate > 1000 mRem/hr Salem Page 14 of 15 Rev. 0 (Draft E)

SGS ECG -EAL Teclmical Bases EP-SC-1 11-235 Salem Radiological EAL Setpoint Calculation Document NEI 99-01, Rev. 05 EALs Calculation for: GENERAL EMERGENCY

-EAL AG1.4 -(1-131 Field Survey Sample Analysis)Objective of Calculation:

Provide a Field Survey Sample Analysis value that equates to an offsite release that would result in a dose of> 5000 mRem Thyroid CDE at or beyond the PROTECTED AREA Boundary.Discussion:

This EAL addresses a radioactivity release field survey 1-131 sample concentration or count rate that would result in a Thyroid CDE dose of greater than 5000 mRem for one hour of inhalation at or beyond the site boundary.

This value exceeds the EPA Protective Action Guides (PAGs). Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.The Iodine-131 field survey sample concentration and count rate threshold is based on 1-131 dose conversion factors (DCFs) from EPA-400. The thresholds are based on a Thyroid-CDE Dose Rate of > 5000 mRelr/hr for 1-13 1.Field Survey 1-131 Sample Analysis results are provided as sample concentration in units of uCi/cc for field samples counted in a Multi-Channel-Analyzer (MCA).Derivation

/ Calculation:

The release sample concentration calculations are as follows.The sample concentration is calculated using the 1-131 Dose Conversion Factor from EPA-400: Solving the following equation for jaCi/cc: mRem/hr = (tCi/cc)(Dose Conversion Factor)Then;5000m Re mn / hr" 1-131 Sample Concentration (jiCi/cc)

(1 .30E + O9m Re in / Ci / cc / hr) 3.85E-06 PCi/cc Where 1.30E+09 mRemn/tCi/cc/hr is the Dose Conversion Factor from EPA-400, Table 5-4, Thyroid Dose, and includes the EPA breathing rate.GE EAL Values: (EAL# RG1.3)1-131 Concentration

> 3.85E-06 pCi/cc Salem Page 15 of 15 Rev. 0 (Draft E)

LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.

Text

5.9. REFERENCES

Navigation menu

LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.

Text

5.9. REFERENCES

Navigation menu

Search