ML18040A219

Forwards Rev to EPIPs EPIP-EPP-01,EPIP-EPP-02 & Site Emergency Plan,Rev 28

ML18040A219
Person / Time
Site:	Nine Mile Point
Issue date:	11/24/1993
From:	Sylvia B NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059A118	List: ML18040A219
References
NMP89360, NUDOCS 9312070055
Download: ML18040A219 (90)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9312070055 DOC.DATE: 93/11/24 NOTARIZED: NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION SYLVIA,B.R. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION R Document Control Branch (Document Control Desk)

SUBJECT:

Forwards rev to EPIPs EPIP-EPP-01,EPIP-EPP-02 6 Site Emergency Plan,Rev 28. (

DIsTRIBUTI0N coDE: A045D coPIEB REOEIUED:LTR + ENGL Q sIzE: + V7 TITLE: OR Submittal: Emergency Preparedness Pla s, Impel ment'g Procedures, C NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 BRINKMAN,D. 1 1 MENNING,J 1 1 D

INTERNAL: AEOD/DOA/IRB 1 1 NRR/DRSS PEPB 1 1 NUDOCS-ABSTRACT 1 1 RZG FIL 01 1 1 O'XTERNAL: NRC PDR 1 1 NSIC 1 1' R

D S

D D

NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE iVASfE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISI'RIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

0 S

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V MIIASAIRA NIAGARAMOHAWKPOWER CORPORATION/NINE MILE POINT, PO. BOX 63, LYCOMING, NY 13093/TELEPHONE (315) 349-2882 B. Ralph Sylvia Executive Vice President November 24, 1993 Nuclear NMP89360 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 1 Nine Mile Point Unit 2 Docket No. 50-220 Docket No. 50-410 DPR-63 NPF-6 Gentlemen:

Enclosed please find uncontrolled copies of revisions to the following Emergency Procedures for Niagara Mohawk Power Corporation's Nine Mile Point Nuclear Station:

ge Emergency Plan Implementing Procedure EPIP-EPP-01, "Classification of Emergency Conditions Unit 1," and

~ Emergency Plan Implementing Procedure EPIP-EPP-02, "Classification of Emergency Conditions Unit 2."

Additionally, revision 28 of the Site Emergency Plan is enclosed.

These Emergency Procedures and the Site Emergency Plan are being submitted as required by Section V to Appendix E of 10 CFR Part 50.

Should you have any questions, please feel free to contact Ms. Coleen T. Ware, Director of Emergency Preparedness, at (315) 349-2066.

Very truly yours, B. Ralph Syl Ia Exec. Vice President - Nuclear BRS/JTP/Imc Enclosures Mr. T. T. Martin, Regional Administrator, Region I (two copies)

Mr. B. S. Norris, Senior Resident Inspector (controlled copyholder)

Mr. R. A. Capra, Director, Project Directorate l-1, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR Mr. J. E. Menning, Project Manager, NRR Records Management

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'pproved By:

K; A. Dahlberg Plant Manager Uni 1 Date Effective Date: 9/1/93 PERIODIC REVIEW DUE DATE DOCUMENT USER:

CONSULT APPLICABLE DOCUMENT CGNTPOL SYSTEM TO OBTAIN LATEST DOCUMENT INFORMATION

e 1

IST OF EFFECTIVE PAGES

~NN . ~hh 0N N 000 N ~Pa e No. Chan e No.

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August 1993 Page i EPIP-EPP-01 Rev 01

1 0

TAB OF CONT NTS S CT ON 1.0 PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2.0 REFERENCES

AND COMMITMENTS . . . . . . . . . . . . . . . . . . .

1

3. 0 DEFINITIONS/DISCUSSION 2

4. 0 RESPONSIBILITIES ........................ 4 5.0 PRECAUTIONS . 5 6.0 LIMITATIONS AND ACTIONS . 5 7.0 PROCEDURE .

7.1 Station Shift Supervisor . . . . . . . . . . . . . . . . 5 7.2 Site Emergency Director . . . . . . . . . . . . . . . . . . 6 8.0 RECORD REVIEM AND DISPOSITION . 6 ATTACHMENT 1: Classification of Emergency Conditions for NMPNS UNIT 1 7 FIGURE 1.A: ABNORMAL RADIATION LEVELS/RADIOLOGICAL EFFLUENT UNIT 1 . 8 FIGURE 1.B:

VALUES FOR NMPNS UNIT 1 STACK RELEASE ...........

TWO AND THIRTY-MINUTE SITE AREA EMERGENCY SOURCE TERM 10 FIGURE 1.C: TWO AND THIRTY-MINUTE SITE AREA EMERGENCY SOURCE TERM VALUES FOR NHPNS UNIT 1 GROUND LEVEL RELEASE ....... 11 FIGURE 1.D: FISSION PRODUCT BARRIER DESIGN UNIT 1 ........... 12 FIGURE I.E: HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY UNIT 1 . 15 FIGURE 1.F: FIRE RELATED EMERGENCY ACTION LEVELS UNIT ........ 21 1

FIGURE 1.G: SYSTEM MALFUNCTIONS UNIT 1 34 August 1993 Page ii EP IP-EPP-01 Rev 01

f ghl

1. 0 ~PURPOS The purpose of this procedure is to describe the criteria to be used by the Site Emergency Director to classify emergencies at Unit 1.

This classification of emergencies is based on the occurrence of specific events or combinations of events which may reduce the overall safety of the station.

2.0 R NC S AND COMMITMENTS 2.1 NUREG-0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in Support of Nuclear Power Plants 2.2 10CFR50.47, Emergency Plans 2.3 10CFR50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities 2.4 EPIP-EPP-18, Activation and Direction of Emergency Plan 2.5 EPIP-EPP-23, Emergency Personnel Action Procedures 2.6 EPIP-EPP-25, Emergency Reclassifications and Recovery 2.7 N2-CSP-7V, Gaseous Radioactive Waste Chemistry Surveillance at Unit 2 2.8 *Emergency Operating Procedures, NMPNS Unit 1 2.9 Special Operating Procedures, NMPNS Unit 1 2.10 Technical Specifications, NMPNS Unit 1 2.11 Emergency Operating Procedures Bases, NMPNS Unit 1 2.12 . EPIP-EPP-10, Security Contingency Event

• Changes to EPIP-EPP-1, "Classification of Emergency Conditions", must be reviewed by NMP1 EOP Coordinator.

2.2 C None August 1993 Page 1 EP IP-EPP-01 Rev 01

3.0 D F N TIONS D SCUSSION

, 3.1 Definitions Confirmed Fire that has been identified by a Nuclear Fire

~ie Fighter.

A system that does not function as it was designed.

"Loss" generally refers to Technical Specification operability.

Vital Any area which contains equipment, systems device or material, the failure, destruction or release of which could directly or indirectly endanger the public's health and safety by exposure to radiation.

Operational Events which are classified as nonemergency situations.

fveldt This class of events is included in the Site Emergency Plan in order to specify personnel action and provide for immediate management review. The class includes situations which are restricted to a small area of the Station or a small number of people, and which have little likelihood of escalation to more severe emergency condition.

Unusual Events are in progress or have occurred which

~vf~nt indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected.

$ ] ert Events are in progress or have occurred which degrade plant safety systems to the extent that increased monitoring of plant safety functions is warranted. Any releases from these events are expected to be limited to small fractions of the EPA Protective Action Guideline plume exposure levels outside the site boundary.

Site Area Events are in progress or have occurred which involve Kmzamu actual or likely major failures of plant functions intended for protection of the public. Releases are not expected to exceed EPA Protective Action Guideline plume exposure levels outside the site boundary.

General Events are in progress or have occurred which

~ml~r~~n involve: actual or imminent substantial core degradation with potential for loss of containment integrity. Any releases from these events can be reasonably expected to exceed EPA Protective Action Guideline plume exposure levels outside the site boundary.

August 1993 Page 2 E PIP-EPP-01 Rev 01

3.1 (Cont)

~lt I Level Al t state of re aredness I t d in antici ation of a ossible I d th t. Th activities on-going at this level include notification I

of appropriate site personnel and off-site agencies, information gathering, briefing of Response Force personnel, preparation of response strategies and perhaps, deployment of response personnel to functions which support the Oepartment's efforts to heighten security; Level II e eclaration a evel A1ert re ires the d I I h securit -related threat. The determination may be arrived at gradually through activities on-going at Level I, or may be made immediately upon recognition of activities or evidence which are overtly security-related (ie., discovery of sabotage in progress). In either case, activities on-going at this level involve activation of the Response Force and implementation of response procedures and strategies in order to mitigate potential consequences of the threat.

A Th t ll d ty tilth dl t th t tl which the Licensee has the authority to determine all activities including exclusion or removal of personnel and property from the area. For Emergency Preparedness purposes the NHPNS/JAFNPP Exclusion Areas are considered to be one Exclusion Area.

3.2 is s 0 3.2.1 NHPC has developed this procedure EPIP-EPP-1 as required by USNRC Regulation 10CFR50.47(b)(4) and 10CFR50, Appendix E, IV.B. This procedure provides a standard emergency classification and action level scheme commonly referred to as Emergency Action Levels (EALs).

3.2.2 As indicated in NUREG-0654 the purpose of EALs is to provide a means to be used for determining the magnitude of an emergency and to allow for appropriate emergency response, including notifications.

3.2.3 An emergency is any situation outside of routine operational events or minor equipment malfunction which could lead to a radiological hazard affecting the .health and safety of plant personnel or the general public, or result .in significant property damage.

August 1993 Page 3 EPIP-EPP-01 Rev 01

3.2.4 There are four (4) classes of EALs or emergencies, and one non-emergency class. These four emergency classes are graduated to provide for fuller response preparation for more serious indicators. These indicators for the four emergency classes are found in this EPIP-EPP-1 as initiating conditions. The classes in increasing order of severity are:

a. Operational Event (Non-emergency)

b. Unusual Event

c. Alert

d. Site Area Emergency

e. General Emergency 3.2.5 The initial classification of an emergency is made as quickly as possible after the occurrence to ensure that the proper protective and corrective actions are taken and also.

to ensure that appropriate off-site authorities are promptly notified.

3.2.6 The initiating conditions listed in this EPIP-EPP-1 are taken from guidance provided in NUREG-0654. Mhere appropriate, specific values are obtained from Unit 1 Technical Specifications, or other documents such as the Unit 1 Offsite Dose Calculation Manual, 10CFR20, etc.

4.0 SPONSIBI ITI S In order to ensure the complete and appropriate handling of emergency classifications, the following position listing provides associated assignment responsibilities.

4.1 t S The SSS of the unit managing the emergency in accordance with EPIP-EPP-18 has the following responsibilities:

4.1.1 Assumes the role of Site Emergency Director until properly relieved.

4.1.2 Initiates the classification of, emergency conditions based on available information.

4.2 ite mer enc Director Evaluates and performs emergency classification or reclassification as necessary.

August 1993 Page 4 E PIP-EPP-01 Rev 01

5.0 PR CAUTIONS 5.1 Figures 1A and 1G are used by the NMP1 Emergency Operating Procedures for entry into Nl-EOP-6, "Radioactivity Release Control". Any changes to Figure 1A or 1G mu'st be reviewed by the Unit 1 EOP coordinator (NMPl Operations Department).

5.2 Since NMPC is the licensee for both NMPNS Unit One and Unit Two, Unit One has been designated as the plant that takes the lead for emergencies that affect both Unit One and Unit Two.

6.0 M T T ON AN CTIONS 6.1 Based on inplant conditions, plant instrumentation,, etc. the Site Emergency Director should determine which Emergency Action Level (EAL) or emergency class will be declared. These EALs are required by USNRC regulation 10CFR50, Appendix E, IV.B.

6.2 As indicated elsewhere in appropriate NMPC emergency plan and procedures the Site Eme'rgency Director may got delegate the responsibility of classifying emergency events. The Site Emergency Director shall use this EPIP-EPP-1 as appropriate in carrying out this responsibility.

6.3 Continual surveillance and assessment of plant conditions may warrant revising the emergency classification as conditions change in order to be consistent with established criteria and to ensure that protective actions initiated, taken, or recommended are commensurate with the situation.

7.0 ~ROCEDUR 7.1 tation Shift Su ervisor 7.1.1 When informed of an emergency situation, is responsible for performing the assessment of the emergency (e.g., plant systems, reactor core and drywell status, and radiological conditions).

7.1.2 Evaluate conditions against the action levels delineated in EPIP-EPP-1 Attachment 1, Action Level Criteria for Classification of Emergency Conditions.'ased on this evaluation classify and declare the emergency as an Unusual Event, Alert, Site Area Emergency or General Emergency, if appropriate.

7.1.3 If an emergency declaration is made, perform appropriate steps as Site Emergency Director until relieved by the Plant Manager-Nuclear or designee.

August 1993 Page 5 EPIP-EPP-01 Rev o1

7.2 r e c Director 7.2.1 Activate the Emergency Plan per EPIP-EPP-18.

7.2.2 Evaluate conditions and evaluate (re-evaluate) the emergency classification against the action levels delineated in EPIP-EPP-1, Attachment 1, Action Level Criteria for Classification of Emergency Conditions for a Unit 1 condition.

7.2.3 If not already done, classify and declare the emergency as an Unusual Event, Alert, Site Area Emergency or General Emergency, if appropriate.

7.2.4 Periodically re-assess emergency conditions, in consultation with the SSS and, if available, Corporate Emergency Director/Recovery Hanager. If appropriate, upgrade, or terminate the emergency classification (utilizing EPIP-EPP-1, Attachment 1 [A-G] "Action Level Criteria for classification of Emergency Conditions" and EPIP-EPP-25 "Emergency Reclassification and Recovery", for guidance).

8.0 R CO REVI M AND D SPOSITION All documentation generated thr ough the implementation of this procedure should be forwarded to:

Director Emergency Preparedness Emergency Preparedness Department Nine Mile Point August 1993 Page 6 EPIP-EPP-01 Rev 01

~NT EP IP-EPP-1 Classification of Emergency Conditions for NMPNS Unit 1

~CONT TS:

Figure 1.A Abnormal Rad Levels/Radiological Effluent (Unit 1)

Figure 1.B Two and Thirty-Minute Site Area Emergency Source Term Values for NHPNS Unit 1 Stack Release 10 Figure 1.C Two and Thirty-Minute Site Area Emergency Source Term Values for NHPNS Unit 1 Ground Level Release Figure 1.D Fission Product Barrier Design (Unit 1) 12 Figure 1.E Hazards and Other Condition Affecting Plant Safety (Unit 1) 15 Figure 1.F Fire Related Emergency Action Level (Unit 1) 20 Figure 1.G System Malfunctions (Unit 1) 33 August. 1993 Page 7 EP IP-EPP-01 Rev Ol

ATTACHMENT 1 F.IGURE 1.A B ORNA AD A ON S AD F N (Unit 1)

Inl tlat ing Condl'ti on Unusual Event Alert Site Area Eaergency General Emergency

~O t ENTRY INTO El%.6, ~Ot ENTRY INTO EOP 6 ~Ot ENTRY INTO EOP-6 oac e f + "RADIOACTIVITY RADIATION RELEASE RADIATION RELEASE RELEASE CONTROL" CONTROL IS REQUIRED CONTROL IS REQUIRED (Applicable to any IS RENIIRED release points(s) 1)hi hl Alarm setpofnt 1)Ef fluent monitors detect 1)Experienced or projected and resulting free value has been exceeded 1)Ten times the hi-hl levels corresponding to release corresponding to eny initiating on stack effluent alarm(s) setpoint on stack greater than 50mr/hr for 1 rem/hr whole body or 5 event) monitor(a) + effluent monftor(a) . 1/2 hr, or greater than 500 mr/hr whole body for realhr child thyroid at site boundary under actual hl-hi Alarm setpolnt Ten times the hl.hi alarms 2 minutes (or five times moteorofogyt value has bocA exceeded setpolnt on Liquid these Levels to the on any liquid effluent effluent monitor(s) thyroid) at the site 2)Off-Site dose duo to monitor, QP ~NO boundary for adverse event ls projected to Confirmation by cheaistry meteorology as determined exceed 5 rem to whole

~OL The stack confirmation by chemistry analysis, that 10 Times bye body or 25 rea to the aenl tor(s) analysis that T/S Limits T/S Limits have been Effluent aenltors detect child thyroid at Sfte alarms(a) are have been exceeded when exceeded shen averaged stack release rates in boundary under actual set at a Lower averaged over a period of over a period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Attachment 1, Figure 1.BE meteorology.

value than the one (1) hour including including contr ibut I on T/S Limfts. contribution from the from Unit 1, Unit 2, and Date sources (surveys, Unit 1, Unft 2 and the J. A. Fitzpatrick. aenltors, etc.) indicate J.A. Fitapatrfck Nuclear R ground Level release Power Plant. 2) Emergency condenser vent rates in Attachment 1, monitor alarm Figure 1.C.

2)The Unit 1 emergency Confirmation by chemiatry ProJected based on plant condenser vent sanltor analysis that 10 times T/S parameters.

~ farm(s) and conf frmation Limits have been exceeded la made by the Chemistry when averaged over the Laboratory that Tech- release Neasured fn the environs Specs. limits have been by Survey Teems.

exceeded when these 3)Routine special saaples or Limits are averaged over surveys, which indicate 2)Pro Jected accutat feted the projected longest effluent(a) release(s) 10 dose Ia ii 1 rem whole emorg. condenser vent times T/S limits. body or 5 rea child release. thyroid outsfde the alta boundary~ (e~g~

3)Routfne or special EPIP-EPP-8 calculations)

+See Precautions aaapfes or surveys which Section Step 5.1 fndicate that Tech Spec Limits have been exceeded st 1993 e S Rev ~

E PIP~-01

ATTACNNENT 1 (Cont)

FIGURE 1.A S RAD CA (Unit 1)

!nltfatlng Condition Unusual Event Alert Site Area Emergency General Emergency

~i editors Redundant radiation that iLOO,: Entry fnto EOP-6 Radiatfon Release monitor the sass Control fs Required.

system or area should be 1)Tuo or more area radiation 1)Experienced or proJected considered as one action monitors or release corresponds to ARN. continuous air monitors 1 rem/hr uhofe body or 5 indicate greater than rem/hr child thyroid at 1)Tuo or more Area 1000 times background or site boundary under actual Radiation Nonltors (ARNs) reading off scale meteorol ogyt reach their hl alarm setpoint values (This 2) Conf lrmed el rborne 2)Off-Site dose due to event does not Include the TIP activity greater than Not Applicable Is proJected to exceed 5 rooa monitor or a monitor 1000 x NPC. (excluding rcm to vhofe body or 25 In alarm due to a planned Radon or daughter rcm to the child thyroid evolut I on) Products) ~ t site boundary under gg actual meteorology.

2)Confirmed building ventilation duct ~ Ir-borne activity Indicates in excess of NPC values (excluding Radon or See Precautions daughter Products)

Section Step 5.1 3)SSS decfdes radiation condition fn the station dictates the need for a general area evacuation.

Page 9 EPIP-EPP-01 August 1993 Rev 01

ATTACHMENT 1 (Cont)

FIGURE 1.B 0 AND THIRTY-MINUTE SIT AR A M RGENCY SOURC T RM VA UES FOR NMPNS UNIT I STACK RE EAS Mind Direction From Site Boundary ~o e ree Ra e gistance ~Ci Sec ~Ci Sec (Meters) (Miles) 168.75 - 191.25 122 7.58E-2 6.4E+7 6.4E+6 191.25 - 213.75 152 9.45E-2 6. 1E+7 6.0E+6 213.75 - 236.25 183 1. 14E-1 5.8E+7 5.8E+6 236.25 - 258.75 884 5.49E-l 4.8E+8 4.8E+7 258.75 281.25 1920 1.19 3. 1E+9 3.1E+8 281.25 - 303.75 2042 1.27 4.0E+9 4.0E+8 303.75 - 326.25 2789 . 1.73 1.3E+10 1.3E+9 326.25 - 348.75 2271 1.41 5.9E+9 5.9E+8 348.75 - 11.25 2758 1.71 1.3E+10 1.3E+9 11.25 33.75 1798 1.12 2.4E+9 2.4E+8 33.75 - 56.25 1417 8.81E-1 1.2E+9 1.2E+8 56.25 - 78.75 892 5.54E-l 5.0E+8 5.0E+7 78.75 - 101.25 221 1.37E-l 5.9E+7 5.9E+6 101.25 - 123.75 137 8.51E-2 6.3E+7 6.3E+6 123.75 - 146.25 114 7.08E-2 6.5E+7 6.5E+6 146.25 - 168.75 107 6.65E-2 6.7E+7 6.6E+6 Atmospheric conditions assumed for stack (107 m high) release are unstable (A) conditions and wind speed of 1 m/sec (2.24 mph).

2. g values are calculated based on the characteristics of a fictional isotope with an average gamma energy of 0.7 MeV/dis and half-life of 30 minutes.

3. g is based on 500 mr/hr exposure for 2 minutes and the f30 is based on 53 mr/hr exposure for 30 minutes.

4. The gz and gm values in the table were corrected for the radioactive decay during the plume travel time from the release point to the receptor under consideration.

August 1993 Page 10 EPIP-EPP-01 Rev 01

ATTACHMENT 1 (Cont)

FIGURE, 1. C TWO AND THIRTY-HINUT S T AREA HERGENCY SOURCE TERM VALUES FOR NHPNS UNIT I GROUND EVEL RE EASE Wind Direction From Site Boundary Op De ree Ran e gistance ~Ci Sec fgCC$ Sec (Meters) (Hiles) 168.75 191.25 122 7.58E-2 1.3E+6 1.3E+5 191.25 - 213.75 152 9.45E-2 1.7E+6 1.7E+5 213.75 - 236.25 183 1. 14E-1 1.9E+6 1.9E+5 236.25 - 258.75 884 5.49E-k 1.0E+7 1.0E+6 258.75 - 281.25 1920 1.19 2.8E+7 2.8E+6 281.25 - 303.75 2042 1.27 3.1E+7 3.1E+6 303.75 - 326.25 2789 1.73 5.2E+7 5.2E+6 326.25 - 348.75 2271 1.41 3.8E+7 3.8E+6 348.75 11.25 2758 1.71 5.1E+7 5.1E+6 11.25 - 33.75 1798 1.12 2.5E+7 2.5E+6 33.75 56.25 1417 8.81E-1 1.8E+7 1.8E+6 56.25 - 78.75 892 5.54E-1 9.8E+6 9.BE+5 78.75 - 101.25 221 1.37E-1 2.3E+6 2.3E+5 101.25 123.75 137 8.51E-2 1.5E+6 1.5E+5 123.75 - 146.25 114 7.08E-2 1.2E+6 1.2E+5 146.25 168.75 107 6. 65E-2 1.1E+6 1.1E+5

1. Atmospheric conditions .assumed for a ground level release are stable (F) conditions and wind speed of 1 m/sec (2.24 mph).

2. g values are calculated based on the characteristics of a fictional isotope with an average gamma energy of 0.7 MeV/dis and half-life of 30 minutes.

3. 9 is based on 500 mr/hr exposure for 2 minutes and the (~a is based on 53 mr/hr exposure for 30 minutes.

4. The gz and gm values in the table were corrected for the radioactive decay during the plume travel time from the release point to the receptor under consideration.

August 1993 Page 11 EP IP-EPP-01 Rev Ol

ATTACHHENT 1 (Cont)

FIGURE 1.D FISSION PRODUCT BARRIER DESIGN (Unit 1)

Inf tfatfng Condition Unusual Event Alert Site Area Emerg General Emergenc Loss of Prfma Failure to achieve 1)Drywell temperature 1)Primary contain>>nt Fuel Damage at the Alert Contairment required operating mode exceeds 310'F integrity fs lost as Classification. (P. 14)

~ante rit ufthin Tech Spec LCO Action OR fndfcated by: AND Statement Time. 2)DryMefl H, and 0, Reactor coolant system exceed 6X and 5X a.Uncontrolled louerfng fntegr3ty at or above the respectively. of dryMell pressure Alert Classf f fcatfon.

OR (P. 15) 3)Prfmary Contafrment b.Uncontrolled Iouer 3ng AND Parameters carrot be of Torus level. Loss of Primary maintained Hfthfn the contafra>>nt integrity at limits of EOP-4 Figures: c.Unfsolable primary or above Alert 1)Heat Capacity Teap. system dfscharging Classification.

Lfmft Ffg 4.3 outside contafrment.

OR 2)Pressure Suppress3on Pressure Ffg 4.5 OR 3)Dryaefi Pressure L3mit Ffg 4.6 OR 4)ERV Tait Pipe Level Limit Ffg 4.7 August 1993 EPIP-EPP-01 Rev 01

ATTACHNENT 1 (Cont)

FIGURE 1.D SS R UC R R (Unit 1) initiating Condition Unusual Event Site Area Eaergency General Eaergency ue sas eo 1)Reactor aystsa activity 1)Reactor systea activity Fuel dsaage at the Alert bno I ue exceeds 2$ AC/g H,O ) exceeds 300 )LC/g Classification.

]

C u total iodine. equivalent ot 1-131. EED QE 0E Reactor Coolant Systes 2)lien both off-gas 2)goth off-gas aonltors trip integrity at or above the aonltora trip on high on high-high alara. the Alert Classification.

a(era QE Not Applicable (P. 15)

QE 3)Nein Steaa Line Rad.

3)Tech Spec Safety Liait aoni tora generate a Lose of Priaery Section 2.1.1.a or Reactor Scree and NSlV Conte Ireent Integr I ty: at 2.1.1.b exceeded. closure. or above the Alert Classification. (P. 13) 4)Continued adequate core cooling cenot be assured.

August 1993 Page 13 EPIP-EPP-01 Rev 01

ATTACNENT 1 (Cont)

FlGURE 1.D s cxxjc RR R s (Uni t 1) lni tlat ing Condition Unusual Event Alert Site Area Eoergency General Eaergency e c o Coo Reactor Coolant Syatce Reactor Coolant Syatca leak RPV water level cornot be Fuel chmage at the Alert S ee t Leakage exceeding Technical rate (identl fled and restored and maintained Claaaif ication. (P. 14)

Specification Liaits. midenti fled) exceeds 50 above TAF. ~ND gpe o Reactor Coolant Syeteca 1)Unidentif led leakage integrity at or above the greater than 5 gpe. Contaiaaent Lsolitlon ac Alert Claaaif Ication ~

R 3.5 paig fry High leakage QP 2)2 gpa increaae in ra'tea Lose of Priaary contaicvoent mfdentl flad leakage integrity at or above the within 24 hr period. Alert. Claaal f ication.

R (P. 13) 3)25 gpa totaL leakage (ident i fled and midentl fled) averaged over any 24 hr period.

st 1993 Rev ~

EPIP-~-01

ATTACINENT 1 (Cont)

FIGURE 1.E A ARDS 0 E ClND S C A (Unit 1) ini t I at lng t Condi I on Unusual Ewnt Alert Site Area Eacrgcncy General Eacrgcncy 2K9CDY A security related A security related event lsIsincnt loss of physical Security event resulting Co~~ij ie event which has been which has been determined control of the plant. In loss of physical control deterained to be a Security to be a Security Alert i.evcl of the facility.

See Precaution Alert Level 1 In accordance 2 In accordance with Nuclear Section Step 5.2 with Nuclear Security Dept. Secur I ty Dept. Procedures.

and EPIP-EPP 10. Procedures.

Any earthquake felt In- Earthquake>> 0.0d g aiarsI IRIcn plant not in cold plant that Is detected on trip of Station seismic shutdownI Station seisaic Instru- Inst rIsacntat I on. Earthquake >> 0.11 g and ~

See Precaution scntatlon by valid clara valid clara trip of Station Not Applicable Section Step 5.2. trip (>>.01g) which also sciaaic Instrmentation.

wcs indica'tcd ~ 't one or aore of the other planta at Nine Nile Point.

High lake water level of Lake water level experienced lgIcn plant not In cold 24d.d ft experienced or or projected near lewis shutdown(

Secs proJected + of 254 ft. Lake water level Low lake water level of experienced or projected Not Applicable Sce Precaution 242.7 ft experienced or greater then 254 ft.

Section Step 5.2. projected.

dbscgcs vital equiixscnt at Mhcn plant not In cold Any tornado experienced or Tornado strike within shutdown:

See Precaution projected within the protected arcs end causing Sustained winds In excess Not Applicable Section Step 5.2. exclusion area. dceagc to plant structures. of 90 Nph.

guur c<E)c Sustained winds greater Experienced or projected When plant not In cold than 75 eph experienced sus'ta incd winds approach shutdowns Not Applicable Sce Precaution or proJected within the 90 sph. Sustained winds In excess Section Step 5.2. exclusion area. of 90 sph.

August 1993 Page 15 EP IP-EPP-01 Rev O1

ATTACINENT 1 (Cont)

FIGURE 1.E A DS AND 0 S F C (Unit 1) ini tlat ing t Condl Ion Unusual Event Atert Site Area Emergency General Ea>>rgcncy IIIEhLB Experienced or proJected Turbine rotat ing cosponcnt turbine rotating cosponcnt failure causing casing failure cwsing rapid plant penetration. This uoutd be Not Appticabte Not Applicable shutdolal. indicated byI NR 1) Turbine overspccd Excess I vs turbine aircr- K vibration ul th noise. 2)Rapid Loss of condenser vacws Nazardous exptos on or Experienced or pro ected Vhcn ptant not in cold

~s~c missile Iapact experienced missile or explosion causing shutdeaI i Not Appt cable or proJected uithin the daa>>gc to station structure Experienced or proJectcd Scc Precaution exclusion area. af fecting plant operation. severe diaage to safety Section Step 5.2. related equipment ~

Vhen plant not ln cold shutdounI See Precaution 1) Exper I snead lsxlsuat 1)Aircraft experienced or Any aircraft crash causing Section Step 5.2. aftft activity over the proJected to strike ~ vital structure damage by facility, as determined station structure. INpact or fire In any of by the Nuclear Security the fottoutng areas:

Department. Not Appt l cable

1) Dryuet I; 2)Aircraft crashes vithln 2)Control Room; the exclusion area. 3)Reactor Bldg; 4)Vesta Bldg; 5)Turbine Bldg; 6 Sc c ouse Joa~c of Uncontl'ot Lcd hazel'dous Entry of Islcontrot ted Vhen plant Is not In cotd release of toxic or hazardous Levels of toxic shutdounI flaaaabte gas released or ftamaabte gss Into Entry of Ixlcontrot tcd Not Applicable See Precaution uithln the exclusion area. facility environs which hazardous Levels of toxic Section Step 5.2. presents habi tabi t I ty or ftamebtc gss Into vital problems. areas uhtch restricts ncccsssl'y access and con s't u'tcs s ct ob cm g 16 EPIP-Rev ('

-OI

ATTACINENT 1 (Cont)

FIGURE IoE RD 0 S C Iunlt 1)

Inl t I sting t Condi I on Unusual Event Alert Site Area Elergency General Eoergency ce 0 1)Loss of all Loss of All Control Roan Loss of All Control Roan nrnslc a ors or Neteorologlcal Oats. Alarw (AnnLaclators) Aleras (Annuncl ators) Not Applicable R ~MD 2)Loss of the foilouing A plant transient is os factions for a Initiated or In progress

~esneg~o continuous period of ~NO

~Alga.agg) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />st Total loss of assesanent

~Cs Qbbg~ capability fran the Control

~ .SPOS out of service. Roan of any of the folioulng pareneterst b.Ability to ~te process canputer.

-- Reactor Pressure, OR

- Reactor Level, OR

- Reactor Peer, OR 3)Loss of the foiiouing - Contalraent Pressure.

camaeicatlon systanst a.Eaergency Not I f )cation Systea Line (Red Phone) b.Neu York State Radiological Eaergency Coaaael cat Ion Line (RECS) c.Cannercial Telephone Lines (Neu York Telephone).

Page 17 EPIP-EPP-01 August 1993 Rev 01

ATTACHHENT I (Cont)

FIGURE I.E HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY (Unit I)

Initiating Conditfon Unusual Event Alert Sfte Area Emergenc General Emergenc Transportat3on of Contamin-ated fnjured indivfdual Not Applicable Not Applicable Not Appl feeble from site to off-site hospftal.

All other Plant Other plant conditions Other plant conditions exist, Other plant conditfons Not Applicable Anomal 3es exist, as determined by the as determined by the exist, as determined by the Site Emergency D3rector, Site Emergency Director, S3te Emergency Director, that warrant fncreased that warrant precautionary that warrant activation of awareness on the part of activat3on of the Technical emergency response facili-the plant operatfng staff Support Center and placing ties and monitoring teams or State and/or local off- Emergency Operations or a precautionary notifi-site authorities. These Facility and other key cation to the public within conditions include failure emergency personnel the 30-mffe EPZ.

to achieve required on standby.

operating mode within Tech Spec LCO Action Statement Time.

Au ust 1993 EPIP-EPP-01 Rev 0

ATTACHNENT l (Cont)

FIGURE 1.E A ARDS A (Unit 1) lni t I at ing t Condl I on Unusual Event Alert Site Area Es>>rgency General Eoergency Goe)~oo~ Evacuation of Control Roas Evacuation of Control Rooa Lyacq~t Not Applicable ia required with control of required and control of Not Appl I cable shutdown syateea established shutdown systems goO fros local stetices. established fras Local stations in 15 ainutes.

Fire conf irs>>d within sejor Fire within Najor plant Fire within s>>jor plant plant structures and ~O structures is confirs>>d and structures Ia conf lrs>>d under control within 10 potentially affecting a safe resulting in the Loss of Not Applicable olnutes ~ shutdown systes as Indicated fLsw:tion of a safe shutdown by: systco es Indicated by Fire within Protected Area Attache>>nt 1, Figure 'I.F.

requiring assistance of 1)Fire resulting in the loss offslte fire depart>>ent to of ftection of ~ chanel extinguish. of e safe shutdown aystea.

OR 2)Fire In any Fire Zone(a) that could Iapact redundant charrels involving safe shutdown cables or equi pa>>nt (see Attacha>>nt 1, Figure 1.F)

August 1993 Page 19 EPIP-EPP-01 Rev 01

ATTACIWENT 1 (Cont)

FIGURE 1.F RE I C (Unit 1)

CROSS REK EX DETECTION FIRE PAGE DETECTION F IRE PAGE DETECTION F IRE PAGE PANEL ZONE ND. PANEL ZONE NO. PANEL ZONE NO.

DA.2013N T2A 27 DA 2161E $ 1A 31 DA.4076E R1A .30 OA.2013$ T2A 27 DA.2161 E 818 31 OA-4076E R'IC 30 DA 2022N T28 27 OA-2161 E T38 31 DA-4076M R18 30 DA-2022S T28 27 DA-2161 N T3$ 31 0-4086 Rl 24 DA-2031 T2D 2$ OA.2162M T3$ 31 OA.4116E R2A 30 OA-2041N 018 28 0.2224 BZA 22 DA-4'116E R1C 30 DA-2041N D1C 28 0.2224 828 22 OA-4116M R28 30 OA-2041N D1D 28 D-2224 T4$ 22 DA-4116M R2C 30 DA-2041S OIA 29 DA-2234 T4A 31 0-4156 R3A 25 OA-2051E T2$ 29 OA-2234 T48 31 0-4156 R38 25 OA-2051M T28 29 D-2345 T6A 22 D.4166 R3A 25 OA-2081S T3A 31 D-2395 T6$ 22 D-4197 R4A 25 OA-20$ 3H T3A 31 D-2395 T6C 22 D 4197 R4$ 25 DA-2083N T3A 31 DX-3011A C1 33 OX.4217A R4A 33 DA 2092E T38 31 OX-30118 C1 33 OX-4217$ R4A 33 DA-2092NG T38 31 OX-3031A C2 23 DA-4237 RSA 30 DA 2092M T3$ 31 OX-30318 C2 23 DA-4237 R58 30 DX-2113A D2D 32 D-3031PL C2 23 0.4267 R6A 25 DX.21138 02D 32 D.3054 C3 23 0-4267 R68 25 DX-2123A 02C 32 D-4016 R18 23 0-5013 $1 26 DX 2123$ D2C 32 0-4026 R1A 23 0-5023 $2 26 DA.2141 D28 30 D.4207 . R4A 23 0.$ 151 F1 26 DX 2141A D2$ 32 D 4207 R48 23 OX-21418 D28 32 D-4036 R18 23 0.2'151 D3 22 D.4046 R1D 23 DA.2151 D2A 30 DX-2151A D2A 32 OX.21518 D2A 32 0

st 1993 20 E PI Rev ~

P-~-01

ATTACNNEMT 1 (Cont)

FlGURE 1.F R A D NC C S (Unit 1)

~ot For purposes of this Figure 1.F, a safe shutchwn system for Unit l consists of any one of the folfoufng decay heat removal paths; 1) Emergency Condenser Control Rod Drive Pump (After d hours), and Reactor Shutdoun Coolant System, 2) Core Spray, Automatic Depressurlzatlon System and Contafnsent Spray Torus Cooling.

DETECTlON FIRE FlRE E R E ECY D-2151 D3 1d DG 103 Cable Tray lffssffe Ffre confirmed resulting fn:

Shield

1) Loss of fcectfon of DG 102 Not Applicable OR

2) Loss of fcnctfon of PB 102 0.2224 Fire conf freed fn one dfvisfon Bat Ra Fire conffrmed resulting fn B2B 1lg gf 1 Bat Rjs resultfng fn the loss of fcsv:tfon of loss of process varfable any charnel of a safe shutdoun systecs indication due to:

due to the foffoufngt 1)Loss of Bst Bff or Bat 812 1)Loss of NG sets 162 and 1?2 OR AND 2)Loss of DG 102 or DG 103 2)Loss of Control Room OR fnstrczaentatfon and Resate 3)Loss of PB 102 or PB 103 Shutdoun Panel lnstru-OR mentatfong 4)Loss of PB 16$ or PB 1?B AND 3)Failure to make the con-TCB 5 T.B. 277' P.B. 101 Area Fire confirmed fn Turbfne building nection frocs the security fire zone that involves safe shutdoun UPS system within 15 min-cables or equipment utes (alternate 115 VAC pouer source to Remote Shutdoun Panel 11).

~D t Fire area losses and a e ressed 0-2345 T6A 5 T.B. 305'. Rx. Bldg.

Supply Fan Area D-2395 T.B. 300'ast Control Not Appl feeble Not Applicable Ventilation Area T.B. 300'outh Page 21 EP I P-EPP-01 August 1993 Rev 01

ATTACINIENT 1 (Cont)

FIGURE 1.F C C (Unit 1) l OE TECT ON FIRE FIRE ON RG N C2 Aux. Control RN. Fire conf ir2sed in fire zone that Fire conf irsNd resulting in loss 3KHH involves safe ihutdee cables or of f2Nct ion of ~ shutdae eyeteeth DX.30315 ~ quIP2aent e due to 0.3054 Rain Control Ra. 1~ ) isolation of both <<aergency condenser 1oopae NN 1b) Loss of shutdown coollny, OR 2a) Loss of all four (4) core spray loops, AND 2b) Loss of all six (6) electro-aatic relief valves D-4016 R18 Rx Bldg., 195'e'N. Corner 1) fire conf ir2sed resulting in loss of fmction of a charnel (1/2 of a D 4026 R1A Rx Bldg., 195'.E. Corner safe shutdoun syste<<(CH11 or CN12)

D.4207 RCA Rx Bldg. ~ 298'.E. Corner OR

2) fire confinoed in tuo (2) fire RCB Rx Bldg., 295'.M. Corner zones that involves safe shutdoun cables or equipeent in both zones D.4036 R18 Rx Bldg., 198'.M. Corner ~s folioet a) fire breaching a Fire Break D-4046 R1D Rx Bldg., 198'.E. Corner Zone (e.g. betueen R'IA and R15)

OR b) fire in opposite charnel zones

( ~ .y. betueen R1A and R48) 22 EPIP- P-oI ust 1993 Qe Rev

ATTACIOlENT 1 (Cont)

FIGORE 1:F R R LA NERGN CT (Unit 1)

DETECTION FIRE FIRE ON R C 0.4086 R1 Dryuet t Fire conf treed resulting ln lose of fmctton of a'chanel (1/2) of ~ safe shutdoun systea due to the fottoutngt

1) The status of the dryuett being ln

~ non-tnerted condition, OR 2a) Lose of a ehutckwn cooling suction Not Applicable or discharge valves, ANO 2b) Loss of any tuo (2) core spray discharge valves, OR

3) Loss of any three (3) etectromattc relief valves.

OR

4) Fire conf traed tn the fire zone that involves safe shutdoun cables or equipaent.

August 1993 Page 23 EP IP-EPP-01 Rev OD

ATTACHNENT 1 (Cont)

FIGURE 1.F G C C (Unit 1)

DETECTlON FIRE FIRE ON AR NERG D-4156 R3A Rx bldg., 2S1 ~

East 1) Fire confirmed resulting In Loss Fire confirmed resulting in loss of function of ~ charnel (1/2) of of a safe ahutdo44n ayates 4k>> to:

R38 Rx Bldg., 2B1'eat a safe ahutdo44n system due to one of the fotto44ingt 1a) lose of shutdo44n cooling, AND a) Loss of PB 16B or 17B 1b) laotatlon of both eo>>rgency (XL condenser loops, b) Loss of ehutdo44n cooling OR OR 2b) loss of ~ Ll four (4) core c) Loss of any t440 (2) core spray discharge valves, spray discharge valves, AND OR ~

2c) Lose of ~ Ll aix (6) ~ lectro-d) Loss of any three (3) electro- matic relief valves matic relief valves OR

2) Fire confirmed in any t44o (2) reduahet charlet fire zones (e.g.

breach of a fire break xone) that Involves safe shutdo44n cables or equipmen'te 0-4166 Rx Bldg., 2S14 East Fire confirmed resulting In the Loss of PB 178.

')-4197 R4A Rx Bldg., 295'.E. Side R4B Rx Bldg., 29B4 N.M. Side Not Appt lcable Not Applicable D-4267 Rx Bldg., 3404 East Rx Bldg. ~ 340'est EPIP- -OI st 1993 e 24 Rev

ATTACNNENT 1 (Cont)

F(GURE 1.F D NRG C (Unit 1)

DETECT lON F IRE FlRE ON ON R R ERG NC D-5013 S1 13 Screenhouse 1) Fire confirmed resulting in loss Fire confirmed resulting in the of fINcticn of ~ chaIvtel (1/2) of loss of a safe shutdoun system

~ safe ahutdoun system due to one due to:

of the follouingt 1a) Loss of DG cooling Nater

~) Loss of an emergency service AND Nater pump, 1b) Failure to make the spool OR piece ti~ from the fire pep b) Loss of any tuo (2) contain- systea to the emergency ser-ment spray raN Nater plsIps, vice Nater system and to the OR diesel generator cooling c) Loss of a diesel generator Nater system cooling Nater plslp (102 or OR 103), 2a) Losi of normal 4 emergency DR service ptas d) Loss of diesel generator 102 AND or 103, 2b) Loss of all normal inventory OR makalu capability to the

2) Fire confinaed in fire zone that vessel, involves safe shutdoun cables or AND equ! pmcnt o 2c) Failure to make the spool place tie to the feechIater

$ 00t Spool piece ties are addressed system fras fire pimp system.

in procedures:

1) NT-OP-10 (Emerg. Serv. Mtr.)

2) N1-OP-21 (Feeduater)

3) N1.OP-45 (Diesel Gen.)

D.5023 S2 14 Diesel Fire Pump Ra Not Applicable Not Applicable 0.$ 151 FT 4 Foam Roas August--l$ 83 Page 25 E PIP-EPP-01 Rev O'I'-

ATTACHNENT 1 (Cont)

FIGURE 1.F FIRE RELATED ENERGENCY ACTION LEVELS (Unit 1)

DETECTION F lRE F IRE OK S R DA-2013k T.B. 2506 k.E. Cond. Stor. fire confirlsed in fire zone that Tank involves safe shutdolal cables, OR DA-2013 S T.B. 250'. Side E. Fire resuitiny in the loss of flslction of e charnel (1/2) of a safe shutdown ayatca due to the follo62lnyt

1) Loss of PB 16B or PB 17B OR

2) Loss of PB 102 or PB 103 OR

3) Loss of DG 102 or DG 103 kot Applicable DA 2022k T2B T.B. 250'.M. Corner 1) Fire conf treed resulting In the loss of flslction of e charnel DA-2022S T2B T.B. 250'. Side (1/2) of e safe ahutd06al a)estele due to the folio66Ingt a) Loss of PB 102 OR b) Loss of PB 16B, OR

2) fire confireed in fire zone that Involves safe ahutdoun cables or equi pscnt s

-OI e 26 E PIP-Rev

ATTACNENT 1 (Cont)

FIGURE 1.F A R N C S lunlt 1)

DETECTION FIRE FIRE DA.2031 T.B. 250'orth of Cable 1) Fire conf ireed resulting ln loss Spreading Rooe of fuetion of ~ charnel (I/2) of a safe shutdoun systea due to the fol i<wings e) Loss of DG 103 OR b) Loss of PB 178 OR c) Loss of PB 102 OR

2) Fire conf lrled in fire tone that involves safe shutckwn cables or cqu I plant ~

Not Applicable DA 2041N 03 50~ 1) Fire conf lreed resulting ln loss ea 0 0 of fmction of a channel (I/2) of 01B DG 102 Foundation ~ safe shut@an aystes due to the fol touingi

~) Loss of PB 102 OR b) Loss of DG 102, OR c) Loss of DG 103

2) Fire conf ireed ln any tMo (2) redundant charnels or fire tones that involves safe ahutdoun cables or equlpnent.

August 1993 Page 27 EP1P-EPP-01 Rev 01

ATTACHMENT 1 (Cont) flGURE 1.F H (Unit 1)

DETECT lON F I RE flRE DA-20Ie1S 01A 19 DQ 103 foundation Fire confir2aed resulting in the loss of f2ection of DG 103.

DA-2051E 12B T.B. 250'. Side E, Fire conf irsed in fire zone that involves safe shutdoun cables or equipsent DA 2051M T2$ T.B. 250'e Side M.

Not Applicable EPIP- -OI e 28 Rev

ATTACKNENT 1 (Cont)

FIGURE 1 F A D KERG C (Unit 1)

DETECTION FIRE FIRE ON OK KER R KC DA-2141 D28 22 DG3102 Roaa Fire confirled resulting in loss of faction of DG 102 Kot Applicable DA.2151 19 DG3103 Rooa Fire conf lrsed resulting In the loss of friction DG 103 DA.4076E R1C R.B. 237'o 340'.E.

stalruell Kot Applicable Fire confireed resulting in loss of flection of ~ shutckwn systea RIA R.B. 237'. Side Fire confirmed resulting In loss of due to:

fmction of a cheaei (1/2) of core spray systcQo 1a) i.oss of shutdoun cooling, AKD DA-4076M R18 R.B. 237'. 1b) Isolation of both eaergency condenser loops, OA.4116E R1C R.B. 237'o 340'.E. Not Applicable OR Stairuei l 2a) loss of shutdoun cooling, AKD R.B. 261', Side Fire conf ireed resulting in loss of 2b) loss of ell four (4) core PB 1718 spray loops, DA 4116M R2C 6'e Fire confiraed resulting In loss of PB 1618 2c) i.oss AND of all six (6) electro-aatic relief valves DA-4237 RSB 317'.

8'.B.

Storage Kot Applicable August 1993 Page 29 EPIP-EPP-01 Rev 01

ATTACNKENT 'I (Cont)

FIGNE 1.F D K R ENC C (Unit 1)

DETECTlON FlRE FIRE ON ON A- OSS ~ Co do 1) Fire confirmed resulting In loss Fire confirmed resulting In loss 0!<<?K03H T.b. 261'ooling lltr. Pp. of fcsction of ~ chanel (I/2) of of fcsetion of ~ safe shutdown a safe shutdown system due to the system due to:

A. 083 C 0 fol Iowlngt DA-2092E T3$ T.B. 2610 -277 Booster Pp 1a) Loss of shutdown cooling, e a) Loss of PS 102 AND 6 ~ ec OR 1b) All four (6) core spray DA-2092M T3$ T.B. 26'lc -277 Recirc. NG b) Loss of PS 103 Loops, S OR AND 6 3B 6 0 B e c) Loss of DG 102 Ic) All six (6) electromatic 6 60 deS OR relief valves, DA.2234 I de d) Loss of DG 103 OR T4B T.B. 277'.E. Side OR Loss of the process variables

2) Fire confirmed In fire xone that indication due to:

involves safe shutdown cable or equi pment i 2a) Loss of lIG Sets 162 and 172, AND 2b) Loss of Control Room and RSP Inst rcmntet I on AND DA-2161 E Fire confirmed resulting In the loss 2c) Failure to make the coraec-BIA 16A Sat. Bd. Rm. BI2 of function of Bat Bd. B12. tion from the security UPS system (alternate 115 VAC 81B 168 Bati Bd. Rm. B11 Fire confirmed resulting In the loss power source) to Remote of fcsmtton of Sat Sd. BIT. Shutdown Panel 11, El.

15 minutes. 250'ithin st P-~-OI 1993 Q 30 E PI Rev

ATTACNENT 1 (Cont)

FIGORE 1.F R A D HER C 5 (Unit 1)

DETECTION F I RE FIRE LE S R NRCEC 24 Fire confirled resulting In loss of DX-21138 faction of PS 103 Not Applicable

~fgJg3~ D2C PB 102 Roce Fire confiraed resulting In loss of DX.2123B fmction of PS 102 D2B 22 D.G. 102 Rooa Fire confirsid resulting In loss of DX-2141S function of DG 102 19 D.G. 103 Rooa Fire confireed resulting In loss of DX-2151B fLsIction of DG 103 August 1993 Page 31 EP IP-EPP-01 Rev 01

ATTACNNENT 1 (Cont)

FIGURE 1.F C (Unit 1)

DETECTIOK FIRE FIRE NERG N ZiUEB C1 10 Cable Spreading Room 1) Fire confirmed resulting In loss Fire confirmed resulting in loss DX-3011$ of f2s3ctlon of ~ cha2v3ei (1/2) of of f2s3ctions of ~ safe shutdee a safe shutdoun system path due system due tot to the foliowlngt 1a) Loss of shutdo3e3 cooling,

~ ~) Loss of DG 102 or 00 103, AND OR 1b) isolation of both E.C. loops, b) Loss of PB 102 or PB 17S OR OR 2a) Loss of all four (4) core c) Loss of shutdoun cooling spray loops, systems AND OR 2b) Lose of all aix (6) electro-

2) Fire confirmed In fire zone that matic relief valves involves safe shutdcwn cables or equipment.

~X RCA RN, Bldg. ~ 295'. Side Fire confirmed resulting In loss of DX-4217B . Emerg. Cond. Vlv. Rm. f2Nction of 2 Kot Applicable

1) Emergency Condenser SI I OR

2) Emergency Condenser SI 2 ust 1993 g 32 E PIP-Rev 0

-01

AT'IACHNENT 1 (Cant)

FIGURE 1.6 (Unit 1)

Inftfatfng Candltfon Unusuat Event Alert Site Area Ersergency General Ereergency us o Failure of Reactor Failure of the Reactor Failure of Reactor A Plant Transient occurs o C tete c Protection Systea and Protect!on Systea and Protection Systes and with a faf lure of the Alternate Rod Insertfan to Alternate Rod lnsertfon to Alternate Rod Insertion Reactor Protection Systes initiate and caeptete a Initiate and casptete a to initiate and caaptete ~ end Alternate Rod Insertion germ and NEER than one Scree. Scree, with continuous to fnltlate and caaptete a control rod la not Inserted power generatfon (but no Scree with continued power to or beyond Position 02. The Reactor Ia not shutdown. core daaage fsmedfatety generatl on and liquid evfdent) and initiation of poison foils to Inject.

Reactor fa shutdown liquid poison la required.

(subcrftfcat betar the heat range).

oss o Coo Loss of ability to reject Caaptete loss of capability

~Ca a~bit t Not Applicable decay heat frca reactor to eafnteln hot shutdown as coolant systea and aafntafn Indicated byr teaperature below 212'F degrees could be indicated 1)Loss of aafn condenser by:

1)Loss of Contaftaent Spray cooling.

2)Loss of shutdown cooling 2)Loss of Eslrgency and Reactor water condensers cteanupo ~IS 3)Loss of Etectraeatfc 3)Loss of Reactor buflding relief vatves.

closed loop cool fng.

4)Loss of atl service water.

August 1993 Page 33 EP IP-EPP-01 Rev 01

ATTACKNENT 1 (Cont)

FIGURE 1.6 lni t tat ing Condition Unusual Event Alert Bite Area Eaergency General Ejsergency 0 0 1)Loss of all off-site m~irr<<Mo peer, R

2)Loss of both on-alta Kot Applicable Not Appl i cabl ~ Kot Appl icabl ~

diesel generators ahen required to be operable.

0 0 0 1)Loss of all off-site Loss of all on-site and Not Applicable poMer, off-site AC peer (as C - te defined by the Alert)

Ega~bX 2)Loss of both on-site exceeds 15 ainutes. Not Applicable diesel generators,

~ltD 3)Turbine Trip.

Not Applicable Loss of OC Pouer Boards Nl Loss of DC pouer (as and 012 uhich could be defined by the Alert) indicated by: stol les exceeds 15 Kot Applicable ainutes.

1)Air operated NSlv closure,

2) Eeergency condenser condcnsata return l V opcni 3)Loss of light indication to electroiatic relief valves ~

igust 1993 34 EPIP- -01 Qe Rev (

ATTACNNENT 1 (Cont)

FIQJRE 1.G fnftiatfng Condition Unusual Event Alert Sfte Area Eeergency General Eaergency ea o tea keactor systoa pressure Not Applicable Not Applicable Not Applicable

~est~ pressure exceeds 1218 paig.

Valid autoaatfc or aewaf s 4 initiation of the Core Not Applicable Not Applicable Not Applicable Spray Syst and injectfon into the vessel.

August 1993 Page 35 EPIP-EPP-01 Rev 01

ATTACNENT 1 (Cont)

FIGURE 1.G UNC S (Unit 1)

Ini t l sting t Condi I on Unusual Event Alert Site Area EaerGency General Eoergency ueo e 0 1)Failure of ~ Safety Valve to reclose would be YRLV~dlm indicated byt a.Anranciator IQ-C.S will anslciate, QR b.Drywall pressure will Not Applicable Not Applicable Not Appl'icable rise, c.Verification with acoustic monitor or theriocouples.

2)Failure of ~ Relief Valve to reclose would be indicated bys a.Drop in electrical output,

b. Annunciator IQ-4-5 will alvsmciatee c.Veri f ication with

~ cous t fc Nxllt or 0 r thersmcoupi as.

E PIP~-OI use 1993 e 36 Rev~ .

ATTACNEHT 1 (Cont)

FlGURE 1.G SYSTEN NALFUXCTTONS (Unf t 1) initiating Condition Unusual Event Alert Site Area Eaergency General Eaergency S eaa re Stem line break outside Stem line break outside prlaary contafraent with Prlaary Contafm>>nt, lsotatlon Valves leakage fsolatlon valves fall to as indicated bye close.

Not Appl 1 cabl ~

~CI~ka Le Not Appt feeble 1)Xaln Steas Line Breaks 1)Xaln Stem Lfne break es indicated by:

~ )Nafn stem line high a.Nafn Stem Line high ftow alara, f tow alara.

b)Nein stem tcamet high b.Nein Stem Tenet teaperature alara Tesperature el era.

itkD 2)Eaergency Condenser Steaa c.Failure of Eaergency Line Break! Condenser vents or Drain l.V. to isolate

~ )Eaergency Condenser high to aaln stem lfne.

stem ftow R 2)Eaergency Condenser Stem b) Eaergency Condenser high Lfne Break as indicated

~ rea tcspel atures bye c)Veri fled by alternate ~ .E.C. High Steaa Flow.

aeans ~

b.E.C. High area tesperatures.

c.Ann K-4-3 August 1993 Page 37 EP IP-EPP-01 Rev 01

ATTACHMENT 1 (Cont)

FIGURE 1.G SYSTEN HALFUNCTIONS (Unit 1)

Initiating Condition Unusual Event Alert Site Area Emergenc General Emergenc Loss of En ineered Failure to achieve required operating mode Not Applicable Kot Applicable Kot Applicable r iri shutdown uithin Tech Spec LCO by Tec~hS ic Action Statement Time.

S nt Fuel Dame e Not Applicable 1)Fuel pool Mater level Hajor damage to spent fuel 1)Experienced or projected belou the Iou level alarm with release of radio- release corresponding to setting and decreasing. activity. 1 rem/hr to Mhole body or OR ~MD 5 rem/hr to child thyroid 2)Fuel damage accident with at site boundary under release of radioactivity 1)Alarm on the refueling actual meteorology.

to Reactor Building. platform high range area radiation monitor 2)Off-site dose due to event ANO ~MD is projected to exceed 2)Rx Bldg Emergency 5 rem to Mhole body or a.Alarm on the fuel pool vent i lat I on activation. 25 rem to the child Lou range ARK. thyroid at site boundary OR under actual meteorology.

b.Rx Bldg Emergency ventilation activation.

Au ust 1993 EP IP-EPP-01 Rev 0

NIAGARA MOHAWK POWER CORPORATION NINE NILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-02 REVISION 01 CLASSIFICATION OF EMERGENCY CONDITIONS UNIT 2 Approved By:

J. H. Hueller Plant anager - U it 2 Date Effective Date: 9/1/93 PERIODIC REVIEW DUE DATE DOCUMENT USER.

CONSULT APPLICABLE DOCUMENT CONTROL SYSTEM TO OBTAIN LATEST DOCUMENT INFORMATION

LIST OF EFFECTIVE PAGES

~PN . ~Ch N ~Pa e No. Chan e No. ~N. ~hN Coversheet . 23 1 a ~ e ~ 24 .

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August 1993 Page i EPIP-EPP-02 Rev Ol

e TABL OF CONTENTS SECTION PAGE 1.0 PURPOSE .

2.0 REFERENCES

AND COMMITMENTS . . . . . . . . . . . . . ...

. . . . 1

3. 0 DEFINITIONS/DISCUSSION 2

4.0 RESPONSIBILITIES 4 5.0 PRECAUTIONS . 5 6.0 LIMITATIONS AND ACTIONS..................... 5 7.0 PROCEDURE . 5

7. 1 Station Shift Supervisor . . . . . . . . . . . . . . . . . . 5 7.2 Site Emergency Director . . . . . . . . . . . . . . . . . . 6 8.0 RECORD REVIEW AND DISPOSITION . 6 ATTACHMENT 1: Classification of Emergency Conditions for NMPNS UNIT 2 7 FIGURE 1.A: ABNORMAL RADIATION LEVELS/RADIOLOGICAL EFFLUENT UNIT 2 . 8 FIGURE 1.B: TWO AND VALUES FOR NMPNS UNIT 2 STACK RELEASE ...........

THIRTY-MINUTE SITE AREA EMERGENCY SOURCE TERM 10 FIGURE 1.C:

VALUES FOR NMPNS UNIT 2 GROUND LEVEL RELEASE .......

TWO AND THIRTY-MINUTE SITE AREA EMERGENCY SOURCE TERM 11 FIGURE 1.D: FISSION PRODUCT BARRIER DESIGN UNIT 2 ........... 12 FIGURE 1.E: HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY UNIT 2 . 15 FIGURE 1.F: FIRE RELATED EMERGENCY ACTION LEVELS UNIT 2 ........ 20 FIGURE 1.G: SYSTEM MALFUNCTIONS UNIT 2 ................ 30 August 1'993 Page ii EPIP-EPP-02 Rev 01

1.0 PURPOSE The purpose of this procedure is to describe the criteria to be used by the Site Emergency Director to classify emergencies at Unit 2.

This classification of emergencies is based on the occurrence of specific events or combinations of events which may reduce the overall safety of the station.

2.0 REFERENCES

AND COMMITMENTS

2. 1 NUREG-0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in Support of Nuclear Power Plants 2.2 10CFR50.47, Emergency Plans 2.3 10CFR50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities

, 2.4 EPIP-EPP-18, Activation and Direction of Emergency Plan 2.5 EPIP-EPP-23, Emergency Personnel Action Procedures 2.6 EPIP-EPP-25, Emergency Reclassifications and Recovery 2.7 N2-CSP-7V, Gaseous Radioactive Waste Chemistry Surveillance at Unit 2 2.8 *Emergency Operating Procedures, NMPNS Unit 2 I

2.9 Technical Specifications, NMPNS Unit 2

2. 10 Emergency Operating Procedures Bases, NMPNS Unit 2

2. 11 EPIP-EPP-10, Security Contingency Event

• Changes to EPIP-EPP-2, "Classification of Emergency Conditions", must be reviewed by NMP2 EOP Coordinator.

2.2 e t None August 1993 Page 1 EPIP-EPP-02 Rev 01

3.0 FINITIONS DISCUSSION 3el efi itions Conf irmed Fire that has been identified by a Nuclear Fire Fire Fighter.

Loss A system that does not function as it was designed.

"Loss" generally refers to Technical Specification operability.

Vital Any area which contains equipment, systems device or Area material, the failure, destruction or release of which could directly or indirectly endanger the public's health and safety by exposure to radiation.

Operational Events which are classified as nonemergency situations.

Event This class of events is included in the Site Emergency Plan in order to specify personnel action and provide for immediate management review. The class includes situations which are restricted to a small area of the Station or a small number of people, and which have little likelihood of escalation to more severe emergency condition.

Unusual Events are in progress or have occurred which Event indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requirin'g offsite response or monitoring are expected.

alert Events are in progress or have occurred which degrade plant safety systems to the extent that increased monitoring of plant safety functions is warranted. Any releases from these events are expected to be limited to small fractions of the EPA Protective Action Guideline plume exposure levels outside the site boundary.

Site Area Events are in progress or have occurred which involve

~Emer e c actual or likely major failures of plant functions intended for protection of the public. Releases are not expected to exceed EPA Protective Action Guideline plume exposure levels outside the site boundary.

General Events are in progress or have occurred which

~Emer enc involve: actual or imminent substantial core degradation with potential for loss of containment integrity. Any releases from these events can be reasonably expected to exceed EPA Protective Action Guideline plume exposure levels outside the site boundary.

August 1993 Page 2 EP IP-EPP-02 Rev 0'1-

3.1 (Cont)

Level I A state of re aredness in antici ation of a ossible Secu t A ert securit res o se to a perceived threat. The major activities on-going at this level include notification of appropriate site personnel and off-site agencies, information gathering, briefing of Response Force personnel, preparation of response strategies and perhaps, deployment of response personnel to functions which support the Department's efforts to heighten security.

Level II The declaration of a Level II Alert re u'res the Securit Alert determination that there exists a credible securit elated threat. The determination may be arrived at gradually through activities on-going at Level I, or may be made immediately upon recognition of activities or evidence which are overtly security-related (ie., discovery of sabotage in progress). In either case, activities on-going at this level involve activation of the Response Force and implementation of response procedures and strategies in order to mitigate potential consequences of the threat.

Exclusion Area The area controlled by. NHPC surrounding the station, in which the Licensee has the authority to determine all activities including exclusion or removal of personnel and property from the area. For Emergency Preparedness purposes the NNPNS/JAFNPP Exclusion Areas are considered to be one Exclusion Area.

3.2 Discuss o 3.2.1 NHPC has developed this procedure EPIP-EPP-2 as required by USNRC Regulation IOCFR50.47(b)(4) and 10CFR50, Appendix E, IV.B. This procedure provides a standard emergency classification and action level scheme commonly referred to as Emergency Action Levels (EALs).

3.2.2 As indicated in NUREG-0654 the purpose of EALs is to provide a means to be used for determining the magnitude of an emergency and to allow for appropriate emergency response, including notifications.

3.2.3 An emergency is any situation outside of routine operational events or minor equipment malfunction which could lead to a radiological hazard affecting the health and safety of plant personnel or the general public, or result in significant property damage.

August 1993 Page 3 EPIP-EPP-02 Rev 01

3.2.4 There are four (4) classes of EALs or emergencies, and one non-emergency class. These four emergency classes are graduated to provide for fuller response preparation for more serious indicators. These indicators for the four emergency classes are found in this EPIP-EPP-2 as initiating conditions. The classes in increasing order of severity are: l

a. Operational Event (Non-emergency)

b. Unusual Event

c. Alert

d. Site Area Emergency

e. General Emergency 3.2.5 The initial classification of an emergency is made as quickly as possible after the occurrence to ensure that the proper protective and corrective actions are taken and also to ensure that appropriate off-site authorities are promptly notified.

3.2.6 The initiating conditions listed in this EPIP-EPP-2 are taken from guidance provided in NUREG-0654. Where appropriate, specific values are obtained from Unit 2 Technical Specifications, or other documents such as the Unit 2 Offsite Dose Calculation Manual, 10CFR20, etc.

4.0 RESPONSIBI ITIES In order to ensure the complete and appropriate handling of emergency classifications, the following position listing provides associated assignment responsibilities.

4.1 Statio S t S e visor The SSS of the unit managing the emergency in accordance with EPIP-EPP-18 has the following responsibilities:

4.1.1 Assumes the role of Site Emergency Director until properly relieved.

4.1.2 Initiates the classification of emergency conditions based on available information.

4.2 Site mer enc Director Evaluates and performs emergency classification or reclassification as necessary.

.August 1993 Page 4 EPIP-EPP-02 I Rev Ol

5.0 PRECAUTIONS 5.1 Figures are used by the NHP2 Emergency Operations Procedure for entry into N2-EOP-RR and N2-EOP-HSL. Any changes to Figures must be reviewed by the Unit 2 EOP coordinator (NHP2 Operations Department).

5.2 Since NHPC is the licensee for both NHPNS Unit One and Unit Two, Unit One has been designated as the plant that takes the lead for emergencies that affect both Unit One and Unit Two.

6.0 IMITATIONS ANO AC 0 S 6.1 Based on inplant conditions, plant instrumentation, etc. the Site Emergency Director should determine which Emergency Action Level (EAL) or emergency class will be declared. These EALs are required by USNRC regulation 10CFR50, Appendix E, IV.B.

6.2 As indicated elsewhere in appropriate NHPC emergency plan and procedures the Site Emergency Director may IIot delegate the responsibility of classifying emergency events. The Site Emergency Director shall use this EPIP-EPP-2 as appropriate in carrying out this responsibility.

6.3 Continual surveillance and assessment of plant conditions may warrant revising the emergency classification as conditions change in order to-be consistent with established criteria and to ensure that protective actions initiated, taken, or recommended are commensurate with the situation.

7.0 PROCEDURE 7.1 Station Shift Su ervisor 7.1.1 Mhen informed of an emergency situation, is responsible for performing the assessment of the emergency (e.g., plant systems, reactor core and drywell status, and radiological conditions).

7.1.2 Evaluate conditions against the action levels delineated in EPIP-EPP-02 Attachment 1, Action Level Criteria for Classification of Emergency Conditions. Based on this evaluation classify and declare the emergency as an Unusual Event, Alert, Site Area Emergency or General Emergency, if appropriate.

7.1.3 If an emergency declaration is made, perform appropriate steps as Site Emergency Director until relieved by the Plant Manager-Nuclear or designee.

August 1993 Page 5 I

EPIP-EPP-02 Rev

7.2 Site mer enc Director 7.2.1 Activate the Emergency Plan per EPIP-EPP-18.

7.2.2 Evaluate conditions and evaluate (re-evaluate) the emergency classification against the action levels delineated in EPIP-EPP-2, Attachment 1, Action Level Criteria for Classification of Emergency Conditions for a Unit 2 condition.

7.2.3 If not already done, classify and declare the emergency as an Unusual Event, Alert, Site Area Emergency or General Emergency, if appropriate.

7.2.4 Periodically re-assess emergency conditions, in consultation with the SSS and, if available, Corporate Emergency Director/Recovery Manager. If appropriate, upgrade, or terminate the emergency classification (utilizing EPIP-EPP-2, Attachment 1 "Action Level Criteria for classification of Emergency Conditions" and EPIP-EPP-25 "Emergency Reclassification and Recovery", for guidance).

8.0 RECORD V EM ND DISPOS TION All documentation generated through the implementation of this procedure should be forwarded to:

Director Emergency Preparedness Emergency Preparedness Department Nine Nile Point August 1993 Page 6 E PIP-,EPP-02 Rev @

EPIP-EPP-2 61T II ENl I Classification of Emergency Conditions for NHPNS Unit 2 CONTENTS:

Figure 1.A Abnormal Rad Levels/Radiological Effluent (Unit 2)

Figure 1.B Two and Thirty-Minute Site Area Emergency Source Term Values for NMPNS Unit 2 Stack Release 10 Figure 1.C Two and Thirty-Minute Site Area Emergency Source Term Values for NHPNS Unit 2 Ground Level Release Figure 1.D Fission Product Barrier Design (Unit 2) 12 Figure 1.E Hazards and Other Condition Affecting Plant Safety (Unit 2) 15 Figure 1.F Fire Related Emergency Action Level (Unit 2) 20 Figure 1.G System Malfunctions (Unit 2) 30 August 1993 Page 7 EPIP-EPP-02 Rev Oi

ATTACNENT 1 FIGURE 1.A BNORHAL RADIATION LEVELS RAD OLOG CAL EFFLUENT (Unit 2)

Initiat3ng Condition Unusual Event Alert Site Area Emergency General Emergency Radioactive uen jLOOz ENTRY INTO EOP, ~OT z ENTRY INTO EOP, NOTE: ENTRY INTO EOP NOTE: ENTRY INTO EOP "RADIOACTIVITY 8RADIOACTIVY RELEASE wRADIOACTIVITY "RADIOACTIVITYRELEASE (Applicable to any RELEASE CONTROL" CONTROL" IS REQUIRED. RELEASE CONTROL" IS CONTROL" IS REQUIRED.

release point(s) IS REQUIRED. REQUIRED.

and resulting frat 1)10 times the Alarm value 1)Experience or projected any initiating 1)Alarm value has been hbs been cxcctd on 8 GENS 1)Effluent monitors detect release corresponds to event) exceeded on 8 GENS stack stack effluent monitor levels corresponding to 1 rem/hr to IJhole Body or effluent monitor, OR greater than 50 mr/hr for 5 rem/hr to ch3ld thyroid 10 times the Alarm value 1/2 hr, ol greater than at site boundary under

~NOT  : The Stack bnd Alarm Value hbs bccn hbs been exceeded on 8 500 mr/hr Ilholc body for bc'tuel metcoroiogye vent aonitors exceeded on a GENS vent GENS vent effluent sonitor 2 minutes (or five times alarms are set effluent monitor, OR these levels to the 2)Off-site dose due to event 8't 8 10 times the Alert value thyroid) at site boundary is projected to exceed 5 loltel'alue than the Alert value has been on a DRHS liquid effluent for adverse meteorology rem to IIhoie Body or 25 T/S L3mits. exceeded on a DRNS liquid ~ onltor. as Indlcatcd res to the child thyroid effluent monitor,- AND bytack at site boundary under jlND Conf irmat ion by chemistry Ilonitol I'tlcasc actual meteorology ~

Conf irmation. by chemistry analysis that 10 times the rates equal to or greater analys38 that T/S limits T/S limit has been than those stated in have been exceeded shen cxcctded lhcn bvel aged Attachment 2, Figure 2.B, averaged over 8 period of over 8 period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> one (1) hour including including contribution Vent mon3tor release contribution from Unit 1, from Unit 1, Unit 2, and rates equal to or greater Unit 2, and J.A. J.A. Fitzpatrick. than those stated in Fitzpatrick. Attachment 2, Figure 2.C, OR 2)Routine or special 2)Routine or special samples Projected based on Plant smlples or survey which or surveys Ilhich indicate Parameters indicate T/S effluent effluent(s) release(s) 10 OR release limits have been times T/S l3mlts. Neasured in the environs cxcccded.

2)Projected acclzmIlattd dose is >> 1 rem Ilhole

+See Precautions body or>> 5 rem child Section Step 5.2 thyroid outside the site boundbrye (cage EPIP-EPP-B ca culbtions EPIP~-02 e 8

~ 'ev

ATTACHNENT 1 (Cont)

FlGURE 1.A ABNORMAL RAD LEVELS RAD OLOG CAL EFFLUENT (Unit 2)

Initiating Condition Unusual Event Alert Site Area Emergency General Emergency

~lh Red) sti ~OT t Entry into EOP NOTE: Entry into EOP ~NOT  : Entry into EOP j evels "Secondary <<Secondary Contairment "Radioactivity Release Contaiwent Control" Control" is required. Control" is required.

may be required.

1)TNo or more Area Radiat3on 1)Experienced or projected

~OT Redundant Radiation Nonitors (ARNs) indicate release corresponds to Nonitors that monitor greater than 1000 times 1 ron/hr to Nhole Body or the sane systen or their respective 5 rem/hr to child thyroid area should be background values. at site boundary under considel ed as one actual meteorology.

ARN. 2)One or more Continuous Air Nonitors (CANs) indicate 2)Off-site dose due to event 1)Two or more Area greater than 1000 times is projected to exceed 5 Radiation Nonitors (ARNs) the3r respective rem to the uhole body or reach the3r HlGH RAD background values. 25 rem to the child setpoint as noted on DRNS OR thyroid at site boundary (This does not include 3)Conf irmed airborne Not Applicable under actual meteorology.

the TlP Room or ARNs in activity greater than the alarm due to a planned value of 1000 times NPC evolution). (excluding Radon or daughter products).

2) Conf irmed building vent i let ion duct airborne act'lv'l'ty lndlcates in excess of NPC values (excluding Radon or daughter products).

OR 3)SSS decides radiation condition in the station dictates the need for a general area evacuation.

August 1993 Page 9 EPIP-EPP-02 Rev 01

ATTACHMENT 1 (Cont)

FIGURE 1.B WO AND THIRTY-MINUTE SITE AREA EMERGENCY SOURCE TERH VALU S FOR NHPNS UNIT 2 STACK R EASE Wind Direction from Site Boundary Qso De ree Ran e distance ~Ci sec ~Ci sec (Meters) (Miles) 168.75 - 191.25 75 4.66E-2 2.41 E+6 2.41 E+5 191.25 - 213.75 75 4.66E-2 2.41 E+6 2.41 E+5 213.75 - 236.25 81 5.03E-2 2.41 E+6 2.41 E+5 236.25 - 258.75 107 6.64E-2 2.55 E+6 2.55 E+5 258.75 281.25 1555 9.66E-l 2.74 E+7 2.74 E+6 281.25 - 303.75 1555 9.66E-1 2.67 E+7 2.67 E+6 303.75 326.25 1600 9.94E-1 2.67 E+7 2.67 E+6 326.25 348.75 2134 1.33 3.47 E+7 3.47 E+6 348.75 - 11.25 2256 1.40 3.55 E+7 3.55 E+6 11.25 - 33.75 1936 1.20 3.18 E+7 3.18 E+6 33.75 56.25 1615 1.00 2.69 E+7 2.69 E+6 56.25 78.75 405 2. 51E-1 8.51 E+6 8.51 E+5 78.75 - 101.25 117 2.27E-2 2.78 E+6 2.78 Et5 101.25 123.75 88 5.46E-2 2.41 E+6 2.41 E+5 123.75 146.25 75 4.66E-2 2.41 E+6 2.41 E+5 146.25 168.75 75 4.66E-2 2.41 E+6 2.41 E+5 NOTES: 1. Atmospheric conditions assumed for stack height of 131 meters for releases;

2. g values are calculated based on the characteristics of a fictitious isotope with T>>z=30 min. and one gamma energy of 0.7 MeV/dis at the main stack gaseous effluent monitor.

3. g is based on 500 mRem/hr whole body exposure for 2 minutes and tfie gso is based on 50 mRem/hr whole body exposure for 30 minutes.

4, The gz and q3 values in the table were not corrected for the radioactive decay during the plume travel time from the release point to the receptor under consideration.

5. The gz and 93Q values shown are calculated using the most conservative X/g for each sector. The Site Boundary Distances shown correspond to this X/g. See Unit II FSAR Table 2F-1 for a summary of Site Boundary Distances.

6. i)a, 8 values derived from SWEC calculation 12177-PR(C)-24-X, Rev. , p. 15, preparer date 6/22/87.

August 1993 Page 10 EP IP-EPP-02 Rev 01

ATTACHMENT 1 (Cont)

FIGURE 1.C TWO AND THIRTY-MINUTE SITE AREA EMERGENCY SOURC TERM V LUES FOR NMPNS UNIT 2 GROUND LEVEL RELEASE Mind Direction from Site Boundary .Qso L0DR Distance ~Ci sec ~Ci sec (Meters) (Miles) 168.75 - 191.25 192 1.19E-l 2.41 E+5 2.41 E+4 191.25 213.75 207 1.29E-1 5.48 E+5 5.48 E+4 213.75 236.25 285 1.77E-l 1.37 E+6 1.37 E+5 236.25 258.75 ~

419 2.60E-1 2.56 E+6 2.56 E+5 258.75 - 281.25 1686 1.05 1.10 E+7 1.10 E+6 281.25 - 303.75 1686 1.05 1.65 E+7 1.65 E+6 303.75 326.25 1743 1.08 1.65 E+7 1.65 E+6 326.25 - 348.75 2094 1.30 2.84 E+7 2.84 E+6 348.75 - 11.25 1945 1.21 8.54 E+6 8.54 E+5 11.25 - 33.75 1695 1.05 1.69 E+7 1.69 E+6 33.75 56.25 1381 8.58E-1 1.01 E+7 1.01 E+6 56.25 - 78.75 988 6.14E-1 6.62 E+6 6.62 E+5 78.75 - 101.25 402 2.50E-1 8.19 E+5 8.19 E+4 101.25 123.75 293 1.82E-1 4.07 E+5 4.07 E+4 123.75 146.25 227 1.41E-1 2.65 E+5 2.65 E+4 146.25 168.75 187 1.16E-1 1.73 E+5 1.73 E+4 NOTES: l. Atmospheric conditions assumed for vent height of 57 meters for releases.

2. Q values are calculated based on the characteristics of a fictitious isotope with T,ip 30 min. and one gamma energy of 0.7 MeV/dis at the radwaste/reactor building vent gaseous effluent monitor.

3. Q is based on 500 mRem/hr whole body exposure for 2 minutes and tive Q3~ is based on 50 mRem/hr whole body exposure for 30 minutes.

4. The Qz and Q3 values in the table were not corrected for the radioactive Jecay during the plume travel time from the release point to the receptor under consideration.

5. The Qz and Q3Q values shown are calculated using the most conservative X/Q for each sector. The Site Boundary Distances shown correspond to this X/Q. See Unit II FSAR Table 2F-1 for a summary of Site Boundary Distances.

6. ils, 8 o values derived from SREC calculation 12177-PR(C)-24-X, Rev. 1, p. 16, preparer date 6/22/87.

August 1993 Page 11 EPIP-EPP-02 Rev 01

ATTACHHENT 1 (Cont)

FIGURE 1.D FISSION PRODUCT BARRIER DESIGN (Unit 2)

Moult Initfating Condition Unusual Event Alert Site Area Emerg General Emerg Loss of Pr3mar Failure to achieve 1)Dryrrell temperature 1)Primary contafrn>>nt Fuel Damage at Alert Cont B 'I required operating mode exceeds 34D'F integrity is lost as classif icat3on

~rnite sit rrfthfn Tech Spec LCO Actfon OR fndicated by: AND Statement Time. 2)DryMell H, and D, a.Uncontrolled Iorrerfng Reactor coolant system exceed 6X and 5X of suppression pool integrity at or above the respectively. rrater level. Alert Classif icat3on OR OR ~MD 3)Primary Conte frrr>>nt b.uncontrolled loMering Loss of Primary Parameters cannot be of contafrment contain>>nt integrity at maintained Nfthfn the pressure. or above the Alert limits of: OR classification.

1)Heat Capacity Terrp. c.Unisolable primary Limit PC-1 system discharging OR outsfde contafrment.

2)Heat Capacity Level Limit PC-5 OR 3)Pressure Suppression Pressure PC-3 OR 4)Prfmary Cont. Pressure Lfmit PC-4 5)SRV Tail Pipe Level LIIAft PC.6 6)Hax. Primary Cont. Mater Level PC-8 Au ust 1993 EPIP-EPP-02

- Rev 01

ATTACRHENT 1 (Cont)

FiGURE 1.0 F SSiON PRODUCT BARRiER DES GN (Unit 2) initiating Unusual Event Alert Site Area Emergency General Emergency Condition

~Fuel aces e or 1)Reactor system activity 1)Reactor system activity Fuel datnage at the Alert Abnormal Fuel and exceeds 4.0 ACi/g dose exceeds 300 AC3/g classification Cled T ratures equivalent l-131. equivalent 1-131. AND OR OR Reactor coolant system

2) Annunciator 851253 2)Nein steam line radiations Not Applicable integrity at or above the "Process Gas Rad. Non. monitors generate or fails Alert classification Activated" and both to generate a Reactor AND off-gas sonitors RE13A Scram and HSlv closure Loss of Primary containment and RE138 trip on high signal. integrity at or above the alarm+ Alert classification.

OR 3)Continued adequate core 3)Tech. Spec. Safety Limit cooling cement be assured.

Section 2.1.1, 2.1.2 or 2.1.4 exceeded.

August 1993 Page 13 EPIP-EPP-02 Rev 01.

ATTACHHENT 1 Cont)

FIGURE 1.0 FISSION PRODUCT BARR ER DESIGN (Unit 2) initiating Condition Unusual Event Alert Site Area Emergency General Emergency Reactor Coolant Reactor Coolant System Reactor System Leak rate RPV Nater level carvtot be Fuel damage at the Alert S tern nte rft leakage exceeding Tech. exceeds 50 gpm from restored and maintained classifIcation Spec. Limits (3.4.3.2) identified or unidentified above TAF. AND sources. Reactor coolant system 1)Any verified pressure integrity at or above the boundary leakage (Tech. Alert classification.

Spec. Def 1.30). Primary contafreent AND isolation at 1.68 psfg from Loss of Primary Contaireent 2)Unfdentf f 'Ied Leakage high leakage rates. integrity at or above the greater than 5 gps. Alert classf fication.

OR 3)Identified leakage greater than 25 gpm Nhen averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

OR 4)Exceeding any other T/S RCS Leakage Limit.

Av t 1993 Pa 14 EPIP-EPP-02 Rev 01

ATTACHNENT 1 (Cont)

FIGURE. 1.E HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY (Unft 2) lnftiatfng Condition Unusual Event Alert Site Area Emergency General Emergency s~ssnr h s A security related event A security related event lslsfntnt loss of physical Security event resultfng C~stNI s ~ which has been determined which has been determined control of the plant. In loss of Physical Control to be ~ Secul'fty Alert to be a Security Alert Level of the f scil I ty.

See Precaution Level 1 fn accordance with 2 in accordance with Nuclear Section Step 5.2 Nuclear Security Dept. Securf ty Dept. Procedures.

and EPlP-EPP-10. Procedures.

~ar hcfcaIke Any earthquake felt fn- Earthquake >0.075 g (>DSE) IJhtn plant not in cold plant that fs detected on bs noted by valid bctUbtfons shutdowns See Precaution Station (>>.01g) seiasfc of: Alarm AlsxsIciatfon Earthquake > 0.15 g Section Step 5.2. fnstrlsetntatfon by valid 842121 on 2CEC-PNL842 JIND (>SSE) as noted by a valid Not Applicable trip of Alarm 842121 on ether light on Response SCtUat lonS Of s Alarel 2CEC-PNL842.

indicated at one or more of the other plants at Nine

~

Spectrlml Annunciator down.

RSA3A plant not fn cold shut-Annunciation 842121 on 2CEC-PNL842 ~MD Red on Response Sptctrcls light N P Ivtctlc a RS A F ood weel High lake water level of Lake water level experienced When plant not In cold feee 248.8 projected ft experienced or or projected ~r levels of 254 ft.

design shutdown( Lake water level experienced or proJected hhsrssts hhsn deshsn hsssls Not Appl I cable See Precaution Low lake water level of of 254 ft. OR damages to Section Sttp 5.2. 242.7 ft experienced or vital equipment at lower proJected. plant elevat fons.

Any tornado experienced or Tornado strike within pro- Mhtn plant not In cold projected within exclusion ttcttd al'eb bnd causing shutdown c See Precaution al'ta ~ damage to plant structures. Sustained winds fn excess Not Appl feeble Section Step 5.2. of design levels of 90 mph.

Hur c ne Sustained winds greater Experienced or projected Mhtn plant not in cold than 75 sph experienced or sUstalned winds appl'obch shutdownc See Precaution proJected within exclusion 90 IIPh. Sustained winds In excess Not Applicable Section Step 5.2. areas of design levels of 90 shah.

August .1993 Page 15 EPIP-EPP-02 Rev 01

ATTACHltENT 1 Cont)

FIGURE 1.E AZARDS AND OTHER COND TIONS AFFECTlNG PLANT SAFETY (Unit 2) initiating Condition Unusual Event Alert Site Area Emergency General Emergency turb~i Experienced or projected Turbine rotatfng coapohcht turbine rotating cosponcnt failure causing casing fat lure causing rapid plant penetration. This could be shutdcen. indicated by: Not Applicable Not Applicable Excessive turbine vibration 1)Turbine overspeed, IItth noise.

2)Rapfd loss of condenser vaclxzno x losion or iss Hazardous explosion or Experienced or projected 3Ihcn plant not fn cold

~i~cg missile exper fenced or m3ssfle or explosion causing shutdolalt projected within the damage to station structures Experienced or projected Not Applicable Sec PI'ccaut loh exclusion ares. ~ ffectfng plant operation. scvtre damage to safety-I't 8 td lndtcatcd byc indicated by: Nhen plant not in cold shutdcwnc Aircraft crash See Precaution 1)Experienced Isxmuaf air- 1)Aircraft strikes a station causing vital structure Stctfon Step 5.2. craft act3vity over the structure. damage by tnpact or fire facility, as dcttrln'tncd tn ahhP of the folfcaItng by Nuclear Security. el'cast Not Applicable OR 1) Conta 3 anent; 2)Atrcraft crashes on-site. 2)Control Room; 3)Reactor Bldg; 4)Rad. llaste Bldg; 5)Turbine Bldg; 6 ScrcchMc 3 Toxic r tancnabte Uncontrolled hazardous Entry of Ixlcontrot led Qhtn plant is not in cold 8$ CS release of toxic or hazardous levels of toxic or shutdoec ftannabte gas released ftINIIebte gas fnto facility Entry of uhcontrot led Not Applicable Sec PI ccautton IIithfn the exclusion area. environs which presents hazardous levels of toxic Secticxl 5.2. habitability problems. or ftannabte gas tnto vital area which restricts hcccss8ry access ahd coh-s'tttu'tcs 8 saftt robtcmo st -02 A 1993.

PI 16 E PIP-Rev

ATTACHNENT 1 (Cont)

F(GURE 1.E HAZARDS AND OTHER COND TIONS AFF CTiNG PLANT SAFETY (Unit 2)

Initiating Condition Unusual Event Alert Site Area Emergency General Emergency Loss of ndicators 1)Loss of all Loss of all Control Room Loss of All Control Room Anraretators or Neteorological Data. Alarms (Annie iators). alarms (annunciators) Not Applicable Alarms in the AND Control Room and 2)Loss of the follouing A plant transient is Loss of Emer enc factions for a initiated or in progress Assessment or continuous period of 8 AND CoctlxÃlicat i on hours: Total loss of assessment C~abiiii capability fran the Control a.SPDS out of service. Room of any of the follouing parameters:

b.Ability to update - Reactor Pressure, OR process coaputer. - Reactor Level, OR OR - Reactor Pouer, OR 3)Loss of the follouing - Contaireent Pressure.

comaei cat iona systems:

a.Emergency Notification System Line (Red phone)

~ND b.NeN York State Radiological Emergency Caaaanication Line (REGS)

AND c.Caanercial Telephone Lines (Neu York Telephone).

August 1993 Page 17 EP I P-EPP-02 Rev 0>

ATTACKHEHT 1 (Cont)

FIGURE 1.E KA2ARDS AND OTHER COHDITIOHS AFFECTING PLANT SAFETY (Unit 2)

Initiating Condition Unusual Event Alert Site Area Emergenc General Emergenc Transportation of Contamin-ated injured indiv3dual Not Appl3cable Hot Applicable Hot Applicable from site to off-site hospital.

All other Plant Other plant conditions Other plant conditions exist, Other plant conditions Hot Applicable

~namal 3es exist, as determined by the es determined by the exist, as determined by the Site Emergency Oirector, Site Emergency Director, Site Emergency Director, that Harrant increased that warrant precautionary that warrant activation of aMareness on the part of activation of the Technical emergency response facili-the plant operating staff Support Center and/or ties and monitoring teams or State and/or local off- Emergency Operations or a precautionary not3fi-site authorities. These Facility and placing other cat3on to the public Hithin conditions include fa3lure key emergency personnel the 10-mile EPZ.

to achieve required on standby.

operating mode within Tech Spec LCO Action Statement Time.

st 1993 Pa e18 EP IP-EPP-02 Au Rev 0

ATTACHNENT 1 (Cont)

FlGURE 'l.E HAZARDS AND OTHER COND ONS AFF CTlNG PLANT SAFETY (Unit 2) lnttiattng Condition Unusual Event Alert Site Area Emergency General Emergency Control Room Not Appl tcable Evacuation of Control Rooa Evacuation of Control Room gVdCUSt[OII ts required with control of ts required and control of shutdown systems established shutdoun systems NOT Not Applicable from local statlces. established from local stations in 15 minutes.

Ftre confirmed utthtn Fire utthtn major plant Fire Mithln major plant major plant structures structures ts confirmed and structures ts confirmed and ~NO under control ls potentially affecttng and ts resulting tn the utthtn 10 minutes safe shutdown systems as loss of a safe shutdown Not Applicable indicated by one or more of system as lndtca'ted by Fire Ntthin protected the fottoMtng 2 itemst Attachment 1, Figure 1.F.

area requiring assistance of off-site fire department 1)Fire resulting tn the loss to exttngutsh. of fax:tton of a division of a safe shutdoun system.

2)Fire tn any fire zone(s) that could impact tuo (2) redundant divisions involving shutdoun cables or equipment.

(See Attachment 1, Figure 1.F)

August 1993 Page 19 EPIP-EPP-02 Rev 01

ATTACKKENT 1 (Cont)

FIGURE 1.F F RE RELATED EMERGENCY ACTION LEVELS (Unit 2)

CROSS R F R NC NDEX DETECTlON FTRE PAGE DETECT lOK F lRE PAGE DETECTlON FlRE PAGE PANEL ZONE KO. PANEL ZONE NO. PANEL ZOKE MO.

PNL 101 201SM 21 PNL 123 21 PML 12e 333XL 21 PNL 101 203SM 21 PNL 123 802NZ 25 PNL 128 332$ I 23 PNL 101 204SM 22 PNL 1?3 - 803NZ 25 PNL 128 334NZ ?3 PNL 101 212SM 22 PNL 123 807KZ 25 PNL 12e 343NZ 23 PNL 101 202SM 22 PNL 123 361NZ 27 PNL 128 340NZ 24.

PNL 10'I 211QI 24 PNL 123 362MZ 27- PNL 128 336XL 25 PNL 101 213SM 25 PNL 123 363NZ 27 PNL 128 339NZ 25 PNL 101 205NZ 25 PNL 125- 402SM 21 PNL 128 342XL 25 PNL 101 206SM 26 PNL 125 403SM 25 PNL 128 337$ l 26 PNL 101 2075M 26 PNL 125 404SM 25 PNL 128 338MZ 26 PNL 101 208SM 26 PNL 125 401NZ Ze PNL 128 335MZ 27 PNL 101 214SM 26 PNL 126 301NM 22 PNL 128 341KZ 27 PNL 103 221SM 21 PNL 126 302MM 22 PNL 128 331$ I 27 PNL 103 222SM 22 PNL 12S 303NM 22 PNL 129 352MM 23 PNL 103 223SM 25 PNL 126 305MM 23 PML 129 371NM 23 PNL 103 224SM 26 PNL 126 306KM PNL 129 360NZ 24 PNL 104 232QI 22 PNL 126 304NM 27 PNL 129 380NZ 24 PKL 104 2315M 24 PKL 126 309$ I 27 PNL 129 359$ l 27 PNL 104 ?39SM 25 PNL 126 312NZ 27 PNL 129 37?KM 27 PXL 104 238SM 26 PNL 127 236NZ 23 PNL 129 351NZ 27 PNL 105 243SM 22 PNL 127 321NM 23 PKL 129 378NZ 27 PNL 105 245SM 25 PNL 127 322NM 23 PNL 129 353SG 28 PNL 105 256NZ 28 PNL 127 325MM 23 PNL 129 354SG 28 PNL 106 252NZ 22 PNL 127 327MM 25 PNL 129 356NZ 28 PNL 106 253XL 27- PNL 127 323MM 26 PNL 129 357XG 28 PNL 106 255SM 27 PNL 127 324M'M 26 PKL 129 35SXG 28 PNL 107 2715M 24 PNL 127 326MM 26 PNL 129 362SG 28 PNL 107 272SM 27 PNL 129 373NZ 2S PNL 108 273QI 24 PNL 129 374SG 28 PNL 108 2745M 27 PNL 129 375SG 28 PNL 10S 281MZ 27 PNL 129 376XG 28 PNL 129 381SG 28 EPIP-EP -02 Py 20 Rev

ATTACHKENT 1 (Cont)

FIGURE 1.F F R R AT D KERG CY CT ON LE S (Unit 2)

~OT I For purposes of this Figure 2.F. a safe shutdown system for Unit 2 consists of any one of the folloMing decay heat removal paths; 1) HPCS, SRV/ADSg RHR Pool Cooling, RHR Shutdown Cooling, 2) RCIC, SRV/ADS, RNR Pool Cooling, RHR Shut@an Cooling.

DETECTION FIRE FIRE FIRE ZONE ON ON OCA ON ALERT S T R A K R NCY Fire confirmed in fire zone Fire confirmed resulting in AND toss of function of a safe arith either (A) OR (B) listed beloM: shut@an system listed bale+I (DIV 1) (A) OR (8) 1a)Loss of HPCS (for more Resulting in the below'! A second fire con- than 30 min.),

loss of function f irmed involving OR of. one division SSD cables or 1b)Loss of RCIC (for more of sub-system equipment in any than 30 min.),

listed of the additional AND following fire Za)Loss of A or B loop of RHR zones I pool cooling (for more than 45 min.),

PNL 125 402SM FA28 Div. 1 (EDG-1) Rm Div. 1 (EDG-1) 403SM OR OR 2b)Loss of A or B loop of RHR PNL 128 333XL FA17 Div. 1 Sugr Rm SP~KOV74A 8 CCE OR shutdown cooling (for more Div. 1 DC pur or 336XL, than 120 mfn.).

PNL 123 806NZ FA61 SMP Rm A SMP A, CLE or 802HZ,803NZg 807NZ ~

Div or 224'/274'PCS 1 LPCS 206SM,207SM,208SII, PNL 101 201SM FA1 Room RHR Hx Rm A Div 1 RHR-A or 214SM,224SM,238SM, 203SM FA1 RHR Hx Rm A 2375M,224SM,238SM, 326NM,337NM,338HZ, PNL 103 221SM FA1 Ax Bay N. El. 215 253XL,255SM,304NM, 300NM,312NM,335 NM, 359NM, or 377NM August 1993 Page 21 EPIP-EPP-02 Rev Ol

ATTACHNENT 1 (Cont)

FIGMRE I.F R RE ATED KERGENCY A T ON EVELS (Unit 2)

'ETECTION FIRE FIRE FIRE ZONE ONE ON AR A OCAT ON ALERT SITE AREA KERGENCY Fire confirmed in fire zone Fire confirmed resulting in AND loss of f2sx:tion of a safe with either (A) OR (B) listed below: shutdown system listed be'nowt (DIV 1) (A) OR (B) 1a)Loss of KPCS (for more Resulting in the A second fire con- than 30 min.),

loss of fLsction fi reed involving OR of one division SSD cables or 1b)Loss of RCIC (for more of sub-system equi pnent (in both than 30 min.),

listed below: zones) in any one AND of the following 2a)Loss of A or 8 loop of RHR fire zones: pool cooling (for more than 45 min.),

PNL 101 RCIC Pp Rm Div. 1 RCIC or 213QI,223SM, OR Pool Lv or Teap 2b)Loss of A or B loop of RHR 175'x 239SM,245SM, 212SM Bldg Gen area N. 175/196e 'ind'Icatlons 205NZ,404SM, shutdown cooling (for sore OR 327NM,339HZ, than 120 min.).

202SM FA1 RHR P1A Rm LPCS 342XL,403QI, OR 336XL,253XL, PNL 103 Rx Bldg. N. 215'x RHR-A 255SM,304NM, OR 309NM,312NMe PNL 104 Bldg. N. RCIC 335NM,359NMe 240'x OR or 377NM PNL 105 243QI FSA34 Bldg. N. 261e ADS PNL 106 252SM FSA34 Rx Bldg. N. El. 289 Div. 1 RHR-A PNL 126 301NM FAB Elec Tel N. El. 214 OR 302NM FA7 Elec Tnnl NM El. 210 Dlv. 1 RCIC 303NM FA10 Elec Tml SM El. 214 PIP- -02 e 22 E Rev

ATTACHNENT 1 (Cont)

FIGURE 1.F F RE RE ATED NERGENCY CT ON LEVELS (Unit 2)

DETECTION FIRE FIRE FIRE ZONE ON AREA. OCAT AL RT SITE AREA NERGENCY Fire confirmed in fire zone Fire confirmed resulting in AND loss of faction of a safe arith either (A) OR (8) Listed belou: shutbwn systea listed beirut (DIV 1) OR (8) 1a)Loss of HPCS (for more Resulting in the A second fire con- than 30 min.),

Loss of fustian fi reed involving OR of one division SSD cables or lb)Loss of RCIC (for more of sub-system equipment (in both then 30 min.),

Listed belou: zones) in any one ~ND of the foLLowing 2a)Loss of A or 8 loop of RHR fire zones:

PNL 126 305NQ A 7 FA16 Di Div cable chase cable chase 237'A) Ci pool cooling (for sore than 45 min.),

OR 2b)Loss of A or 8 loop of RHR PNL 127 FA48 ec TNL Ver shutdcwn cooling (for more 14'36HZ E

Div cable chase than 120 min.).

8'r attached 237'21'A16 FA17 Di 1

cable area ZCO'22Nll61'06W RHR-A C'r 325W FA2 v 1 cab e chase 44 I or D'See PNL 128 332W FA16 v cable chase RCIC Table 82) 334NZ A 7 Div Ba Rm 6 i 343HZ FACC RSS Rm A FA 6 Di cable chase 61'52W PNL 129 A 6 Oiv cab chase 77'71NM 306'ugust 1993 Page 23 EPIP-EPP-02 Rev 01

ATTACHMENT 1 (Cont)

FIGURE 1.F F RE RELAY EMERGENCY ACT ON VEI.S (Unit 2)

DETECTION F IRE FIRE FIRE ZONE OME ON R A OCAT ON AL R S T AREA KERGENCY Fire confirmed ln fire zone Fire confirmed resulting in AMD toss of fmctton of a safe Ntth either (A) OR (8) listed betoM: shutdo44n system listed betoM:

(DIV 1) (A) OR (8) 1a)Loss of HPCS (for more Resulting ln the A second fire con- than 30 min.),

loss of f4mctton f irmed involving OR of one dl vision SSD cabtes or 1b)Loss of RCIC (for more of sub-system equi psent (ln both than 30 min.),

t lated beto442 zones) ln any one AND of the fotto44tng 2a)Loss of A or 8 loop of RHR fire zones: pool cooling (for more than 45 min.),

PNL 10 211 SM FA1 Aux Ba N 984 OR PML PNL 104 107 231'A 271 SM FSA34 Aux Ba Rx Sl N

NM 2404 328' Not Applicable Not App'llcabte 2b)Loss of A or 8 loop of RHR shutdo44n cooling (for more PN 108 273 SM SA34 I N 28'C than 120 min.).

PN 128 OMZ FA22 Rm 614

~NL 129 360M FA25 HVAC Rm 288'S

~0~M F 76 Co do 064 24 E PIP- -02 ugust 1993 Rev

ATTACHNENT 1 (Cant)

FIGURE 1 ~ F F R R AT D ENER ENCY ACT ON EVELS (Unit 2)

DETECTION FIRE FIRE FIRE ZONE ON 2 A OCAT ON AL RT S T AREA NERGENCT Fire confirmed fn fire zone Fire confirmed resulting in AND loss of fwctfon of a safe with either (A) OR (8) listed belong( shutdown system Listed belouc (OIV 2) OR (8) 1a)Loss of HPCS (for more Resulting fn the A second fire con- then 30 mfn.),

loss of fcnctfan ffreed Involving OR of'n division SSD cables or 1b)Loss of RCIC (for morc sub-systems equipment (ln both than 30 min.),

listed belout zones) fn any one AND of the foLLaufng 2a)Loss of A or 8 loop of RHR fire zones: pool cooling (for sere then 45 min.),

PNL 125 403 SM FA29 Dv 2 DG Rm 261'v Oiv 2 (EOG-3) 402SM,333XL, OR 806NZ,212SM, 2b)Loss of A or 8 loop of RHR PNL 128 336XL FA19 2 Sugr Rm 261 ~

222SM,232SM, shutdown cooling (for more 243SM, or A or 8 than 120 min.).

PNL 123 802NZ FA71 ntake Ares 261 ~ Dlv 2 SMP (MDAF) or C (See attached 803NZ FA71 SMP Rm 8 24'MP Table NZ) 807HZ FA60 Rm 8 224'/274'x PNL 101 213SM FSA35 BLdg General Area South Rx Lv or Pool Lv 8 Pool tenp fndlca-PNL 125 05N 404SM FA30 175'/195'PCS Rm 3 (EDG.2) 175 261'A)

'v Rm tfan for HPCS HPCS RHR ar PNL 127 327NM FA21 HPCS Cable Area 244'v PNL 128 339N FA75 Bat Rm S~r 261'PCS 342XL FA21 Rm 261~

PNL 103 223SM FSA35 Rx Bl So 215'ux Pool Lv 8 Pool F or D (See PNL 104 239SM FA3 Ba Sa 240'x Tenp Indication attached Table NZ)

PN 105 245SM FSA35 l So August 1993 Page 25 EPIP-EPP-02 Rev 01

ATTACHHENT 1 (Cont)

FIGURE 1.F FIRE RELAY D EHERGENCY ACT ON LEVELS (Unft 2)

DETECTION FIRE FIRE FIRE ZONE ON ON OCAT ON A ERT S T RE HERG NCY Fire confirmed fn fire zone Fire confirmed resulting fn AND loss of fINctfon of a safe Nlth.either (A) OR (8) listed befo66: shutdown system listed befou:

(Dlv 2) OR (8) 1a)Loss of HPCS (for more Resulting fn the A second fire con- than 30 min.),

loss of fIslctfon ffreed involving OR of on dfvfsfon SSD cables or 1b)Loss of RCIC (for sere sub-systems equipment (fn both than 30 min.),

6'A) l I sted bef6x6: zones) In any one AND of the foffoufng 2a)Loss of A or 8 loop of RHR fire zonest pool cooling (for more than 45 mfn.),

PNL 101 Ax 8 So RHR HxRH 175 OR 07SII Ax 8 So 175 RHR Rm B 2b)Loss of A or 8 loop of RHR Ax B So 175 RHR P Rm C shutdown cooling (for more A .B So 1986 A and C than 120 min.).

PNL 103 224QI Ax Ba So 2 56 RHR - 8 or C (See attached PN 104 238QI FSA35 Rx I So G 40' Table t2)

PNL 127 323 NII Cable Area 3 FA18 iv Cable Ar ea 40' FA23 v Cab e Area 446 PNL 128 FA18 Cab e Chase 61'SSRm ugust 1993 26 EPIP-~02 Rev I'

ATTACHMENT 1 (Cont)

FlGURE 1.F IRE RELATED MERGENCY ACT ON VE S (Unit 2)

DETECT lON F lRE FIRE FlRE ZOHE ONE RE OCAT ON ALER S 'TE AREA EMERGENCY Fire confirmed in fire zone Fire confirmed resulting in AHD loss of fcxx:tion of a safe Nith either (A) OR (8) listed belch) shutdNNI systes listed belch)

(Dlv 2) (A) OR (8) 1a)Loss of HPCS (for more Resulting in the A second fire con- than 30 min.),

Loss of fcsx:tion f irmed involving OR of on division SSD cables or 1b)Loss of RClC (for sore sh-systems equipment (in both than 30 min.),

L lated belcwc zones) in any one ~MD of the foLLouing 2a)Loss of A or B loop of RHR fire zones: pool cooling (for more then 45 min.),

PNL 106 FA81 Rx 8 N 89 600V S r Rm OR 255SM SA35 R l S 289' 2b)Loss of A or B loop of RHR PNL 126 304NM FA9 ec use 214' shutdown cooling (for more 309MM FA18 0 v cable chase 214' 88'3XL RHR - B or C A or B or D or C than 120 min.).

2NZ A16 D v Cab chase or HPCS or F PN 28 A14 0 v Bat Rm 261 4'35HZ (See attached PNL 129 FA18 Div Cable chase '9MM Table g2) 377MM FA18 iv Cable chase 06~

NL 1 7 FSA35 Rx S M Gen Area SE 328'74SM PNL 108 FSA35 Rx 8'1N FSA35 Rx N Pt Tear+ 245' 353'61HZ PNL 123 FA55 62N FA55 Pi Tcxnel 245 Not Applicable Not Applicable FA55 Pi Tunnel 306'2SM

'3N Div 239'41HZ PNL 128 FA23 CB AC Rm 6 ~

33 MII FA17 DG-CB Cor do 26 ~

PNL 129 51N A72 CB Cor 8 nst Sh 288~

CB D AC August 1993 Page 27 EPIP-EPP-02 Rev Ol

ATTACHNENT 1 (Cont)

FIGURE 1.F FIRE RELATED ENERGENCY ACT ON EVELS (Unit 2)

DETECTION FIRE FIRE FIRE ZONE ONE LOCAT ON S T AREA ENERGENCY PNL 105 Drywall Fire confirmed involving SSD cables or Fire confirmed resulting in (Div I, ll, 8 lll) equipment loss of f2s2ctfon of a safe shutdoun system listed befou:

PNL 125 401NZ FA28 Diesel Generator Fire confirmed in a fire zone FA29 Control Room resulting ln the loss of fuetfon of 1a)Loss of HPCS (for sore FA30 (Dlv I ~ ll ~ 8 lll) any DG OR than 30 min.),

OR Fire conf frmed in any 2 of 3 fire 1b)Loss of RCIC (for sore areas involving SSD cables or than 30 min.),

equi pment ~HD 2a)Loss of A or 8 loop of RHR PNL 129 353SG pool cooling (for more than 354SG 45 min.),

Relay Roaa Fire confirmed involving SSD cables OR 356NZ (Div I ~ I I, I I I I) or equipment Zb)Loss of A or 8 loop of RHR 357XG OR shutdcwn coolfng (for more 358XG Fire confirmed resulting in the than 120 min.).

362SG evacuation of the control room 373HZ liain Conti'ol Room 374SG FA26 (Div I, ll, t ill) 375SG 376XG 381 SG 28 EPIP- -02 Rev

ATTACHMENT 1 (Cont)

FIGURE 1.F F RE RE ATED EMERGENCY CT ON EVELS (Unit 2)

VIS OM STSTEN RELATED FIRE ZONES P H. C Per 201SM 03SM 1SM 402SM 333XL RC RHR A 8 RCIC 202SM, 252SM, 3011M, 302NM, 303NM, 305NM, 306MM, 236HZ, 321NM, 322li, 325IN, 332NM, 334NZ, 343NZ, 352NZ, 371NM Rx v Pool v8 indica on RC C 8 LPCS 212QI v A 806HZ Rx v P v T ind RC C AOS CRD 22SM 232 QI 243 SM k A 211QI 231QI 71QI 273QI 260HZ 340NZ 360MZ 380NZ RHR-B, C, 8 (Oiv II PMr) 206QI, 207QI, 208SM, 214SM, 224QI, 238SM, 238SM, 237NZ, 323NM, AJP AC 32CNM 326NM 337NM 338HZ 403MS 336XL HPCS 205HZ 404SM 327MM 339MZ 3C2XL RHRPB C 8 HPCS 253X 55QI 304KM 09NM 312NM 335NM 59MM 377N'M Rx v Poo v C I ication RH 8 HPCS 13QI QJP Div 8 0 802 N 803NX 807HZ F'I Poo v indi ca on 223 SM 239SM 34QI K/A 272SM, 274QI, 281NZ, 361HZ, 362HZ, 363NZ, 331NZ, 341NZg 351NZ 37$ IZ 331NM Both Diva 0 ell 256NZ 44M 35CMZ Both Dive DG 83 Contre Res 401NZ Both Dive Re e Roan 353SG 354S SNZ 356NZ 357XG 358XG 362SG Both Dive. Control Roan 372NZ, 373NZ, 374SG, 375SG, 376SG, 381SG August 1993 Page 29 EP IP-EPP-02 Rev 01

ATTACHKENT 1 (Cont)

FlGURE 1.G SYSTEN NALFUNCTlONS (Unit 2) lni tlat ing Condition Unusual Event Alert Site Area Emergency General Emergency ailuI'c 'to Ai'tiate Failure of Reactor Failure of the Reactor Failure of Reactor A plant transient occurs or C tete a Scr<<s Protection System and Protection System and Protection System and Nith a failure of the Alternate Rod insertion to Alternate Rod lnsertlon to Alternate Rod Insertion to Reac'tol'ro'tcctioA System initiate and cocTIlete a 'Ihltiate CAd complete a initiate and cooTIlete a and alternate rod insertion Scr<<s and K~KR then one Scr<<n. Scr<<n vith continuous to ihltiatc CAd complete a control rod is not inserted AND pwer generation (but no Scr<<s, Nith continued poMcr to ai less't pos'ltioh 02 col e damage lmjscdlatcly generation, and stand by jIND The Reactor is not shutdoICI. evident) and ih'l'tiatioA of liquid control fails to Reactor is shutdoun (sub- Stagy Liquid Control inject.

crltical belou the heat- System.

ing range).

Loss of Coold Loss of ability to reject COOTIlete loss of capability

~ea bllft decay heat fran Reactor capability to maintain Kot Applicable coolant system and maintain hot shutckwh as indicated Kot Applicable temperature below 200'F bye degrees as indicated by:

1)Loss of main condenser 1)Both RHR-A ahd RHR-B AND shutdouh cooling modes not 2)Loss of Safety Relief fINIctional. Valves AND AND 2)Ko alternate decay heat 3)Loss of Rclc removal systems are AND available. 4)Loss of Ste<<n Condensing.

gust 1993 e 30

~

EPIP~-02 'ev

ATTACHNEKT 1 (Cont) fiGURE 1.G lni t l sting Condition Unusual Event Alert Site Area Emergency General Emergency oss of all Off-Site 1)Loss of atl off-site er or loss of peer. Not Applicable Kot Applicable i Not Appl cable on-site AC r

~ab~li t 2)Loss of Div l and Div ll, on-site diesel gen. uhen required to be operable.

oss of all off-site 1)Loss of all off-site Loss of all on-site and e and loss of peer. off-site AC pater (as all AC on site e Kot Applicable ~ND defined by the ALERT)

~cc blttt 2)Loss of Div l and Div Il, exceeds 15 minutes. Not Applicable on-site diesel generators.

~kD 3)Turbine Trip.

oss of On-Site Loss of DC Poker boards Loss of DC Pouer (as Vital DC Power 2BTS*SMG002A 4 2BTS~SMG0028 defined by the ALERT)

Not Applicable as indicated by the a~lies exceeds 15 follouing arwxeciatorst minutes. Not Applicable 1)Alarm 852108 Div l Emer-gency 125VDC.

2)Alarm 852208 Dlv ll Emer-gency 125VDC.

August 1993 Page 31 EP IP-EPP-02 Rev Ol

ATTACNNENT 1 (Cont)

FIGURE 1.G SYSTEN NALFUKCTIOKS (Unit 2)

Initiatfng Condition Unusual Event Alert Site Area Emergency R~eactor S teo(RSP Reactor system pressure Not Applicable Not Applicable Not Appl feeble Preaacre exceeds 1218 psig.

nitiatfon of ECCS Valfd autclaatfc or manual and dfschar e to initiation of one or morc Not Applfcable Not Applicable Not Applfcable vessel of the following, Nfth injection into the vessel.

1)HPCS 2)LPCS 3)LPCI A, gs and/or C.

g 32 EP Rev ~

IP-~-02

ATTACHXENT 1 (Cont)

FIGURE 1.G Inl tiat lng t Condl ion Unusual Event Alert Site Area Emergency General Emergency allure of a Reac 0 Failure of a Safety/Relief S tern Sa et Re le Valve to reclose as Indicated by either one:

fol loui reduc I

~rn ressu e 1)Annunciator 601548 Not Applicable Not Appl !cable Not Applicable 4Safety/Relief Valve Opene actuates (acoustic monl tor relay actuation).

2)Suppression Pool Temper-ature rises.

3) Veri f I cat Ion ul th acoustic monitor. (Open indication (reco on panel 601).

4)Drop In electrical out-put, (Approx. 70 We, lf fully open SRV).

5)Slight decrease in reactor le'vel.

OR 6)Stems Fiou/Feed Flou mismatch August 1993 Page 33 EPIP-EPP-02 Rev 01

ATTACRHENT 1 (Cont)

FlGURE 1.G SYSTENS NA FNCT)ONS (Unit 2) initiating condition Unusual Event Alert Site Area Emergency General Emergency Stcam lne Brea Steam line break outside Stermr line brcak outside Hot Applicable ffot Applicable prfmary contafrmcnt rrfth Primary Contaftmente isolation Valves Leakage as isolation valves fall to determined by contfrxxxe close.

lndfcatlon of the folforrfng:

1)Nein Stermr Line Break: 1)Hain steam line break:

a)Hain Steam Florr Rate High a)Hain steam florr rate OR b)Hain steam trsrrcl ambient b)Hain steam line anhfent temperature high teap high OR c)Hain stcam trsvrcf differ- c)Nafn Steam Trsvrel differ-ential terrperaturc high ential terpcrature high OR OR 2)RClC Stcam Line Break: 2)RCIC stcam lfne break:

a)RClC pipe chase tcap. high a)RClC pipe chase terp high OR b)Equipment Roas tcnp. b)Equipment Roarr terp high-high high-high OR OR c)indlcatfon of continued c)Steam line differential Stcam Line differential pressure prcssure OR d)verify by alternate means use 1993 e 34 Rev ~

E PIP~-02

ATTACHMENT 1 (Cont)

FIGURE 1.G SYSTEM MALFUNCTIONS (Unit 2)

Initiating Condition Unusual Event Alert Site Area Emerg General Emergenc Loss of En Ineered Failure to achieve

~eetet Feature required operating mode Not Applicable Not Applicable Not Applicable r iri shutdown within Tech Spec LCO

~Te~ch S ec Action Statement Time.

S nt Fuel Oama e Not Applicable 1)Fuel pool water level Major chmage to spent fuel 1)Experienced or projected below the low level alarm with release of radio- release corresponding to setting and decreasing. activity. 1 rem/hr to whole body or

~ND 5 rem/hr to child thyroid 2)Fuel chmage accident with at site boundary under release of radioactivity 1)Alarm on the refueling actual meteorology.

to Reactor Building. platform high range area radiation monitor 2)off-site dose due to event AND AND is projected to exceed 2)Rx Bldg Emergency 5 rem to whole body or a.Alarm on the fuel pool ventilat3on act3vat3on. 25 rem to the child low range ARM. thyroid at site boundary under actual meteorology.

b.Rx Bldg Emergency ventilation activation.

August 1993 Page 35 EP IP-EPP-02 Rev Ol

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