Text

Emergency Exercise Scenario for Exercise During Wk of 850519.
	ML20006F746
Person / Time
Site:	North Anna
Issue date:	05/19/1985
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20006F745	List: ML20006F744; ML20006F746;
References
	NUDOCS 9003010095
	Download: ML20006F746 (269)
	v • d • e

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.. .1 r f.. i INDEX .

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1. Ruferences .;

2. List of Simulations ,

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3. Useful Information

4. Scope

5. Objectives

6. Emergency Exercise Scenario Narrative I

7. Emergency Exercise Scenario Events i

8. - Participants l

9. Messages ,

c 10. Controller Data

11. Diagrams of Facilities 12; Controller an'd Observer Information

13. Observer Critique Sheets-

14. Critiques t

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. . ? . 'n .. .. W 'L. ! . . . : ,- . .t , .~. :,.. - . .. . i. ? q NAEE Section 1 + , Pcgs 1 of 1 04-01-85 i k._)l: REFERENCES i ~

1. Corporate Emergency Responso Plan

2. Corporate Plan Implementing Procedures

3. North Anna Power Station Emergency Plan

4. North Anna Power Station Emergency Plan Implementing l Procedures :

5. Commonwealth of Virginia Radiological Emergency Response Plan

6. County Radiological Emergency Response Plan for the counties of Louisa, Spotsylvania, Orange, Caroline and Hanover

7 NUREG - 0654 - -

u , oO .i a e 4A4 A,wAn a 4M &Ev mts-,- a a- "- Ea^* A 4 A & --- +r4o' AW-*"$4O4 m- +tA-+4 4m 3 lf : < } } 'i.- . 4 '[: I i 5 I i !i ~ 6 t I Y

2. LIST OF ' SIMULATIONS -

<A ? ? l t a k ) } 6 O v f NAEE Ssetion 2 Pcge 1 of 1- , 04-01 { ,~ e. \ ,/' t LIST OF SIMULATIONS, '! 9

1. - Simulate . a . request - for assistance for additional field monitoring personnel from Surry Power Station.

2. Simulate a request for food and bedding supplies for station personnel..

3. Account _for station employees on vacation and simulate the recall of as many as possible.

4. Simulate the following calls for assistance: -

a. Westinghouse

b. INPO jm. 5. Simulate the' wearing of PC's except in actual contamination areas.

= -t ) Y2' 6. Simulate activation of the North Anna Early Warning System. t a 1 ,n v i l 5 . .. ~ . . t 5 + y; e t f v 1 t- r 3. USEFUL INFORMATION t s l. r 1 ( '. i i > 'I ^ vr ; i ( '. L l l 1, (l

i. \

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l .- 1 L- ,~ j '- . - - - - - . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ 9 , m - 4 1 NAEE Ssetion 3 1 Pags 1 of 5 l 06-01-85 -I % ) . . i USEFUL INFORMATION j

1. Route to North Anna Power Station 1

-2. Map to locate Virginia Power's Corporate Office

3. Map to locate the Commonwealth of Virginia's Emergency.

Operations Facility

4. Nearby accommodations l

L - i-1 e .N LO r NAEE Section 3 Page 2 of 5*- . 04-01-85 USEFUL'INFORMATION , . i ROUTE TO NORTH ANNA POWER STATION SY AIR: Byrd International Airport - Richmond, Virginia r BY CAR: Refer to the asp below. The station is approximately 60 miles North of Richmond. Take Interstate 64 West to the Shannon Bill Rait (Exit #29). Take houte 605 North to U.S. 3Ashway 522. Take U.S. 522 North (lef t) to Route 700 0 the Right. L Take Route 700 to North Anna Power Station. l [ BY TRAIN: AM-TRAK with a connection in Richmond. O - = kNORTH ANNA ~ ses

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y . O ,_0 5 ._m AIRPORT U I-NAEE Section 3'- f CSTERSTATE 8' y - Page 3 of 5 b 1-85 8 l-COLitEUM 2-JOHN MARSHALL HOTEL

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O $ 4-TDBACCO COMPANY FIEST* P- PARKMG . l lj L-L .- A, urise sT (t , si a 5 ~ si s gl- e e . 38 ~ Ct.,W ST i g I > t n a 5 5 I ! $ g MARSH L ST t I t 41 4 4 Y t 4 f t 4 d 5 ' RCAO ST m m umamlus muma mi j . Y I . GRACE ST STATE l l #" FRANKUN ST ! I ' 6- l- "g l MAIN 'ST t B MMulm A suas namn sunse unsun .:. can{_y CANAL ST s ,,,, Q I~ r I ! . ;c

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\ u ' -"P MTERSTATE' ' $ - ~ 8 95v 00WNTOWN h EXPRESSWAY L l f VIRGINIA ELECTRIC AND POWER COMPANY O CORPORATE EMERGENCY RESPONSE CENTER ame_ --,----,w--,---,---,-----e- - ---ve--ww ~~<w-* + - - * * ---+e -e . -. . . . _ . = - . - - - - - . . . - . - . . - _ . _ - - - - . . . _ .c NAEE Section 3 Pegs 4 of 5 , 04-01-85 : 3 .c o ' /4, Cit, of Itichnong .g v ' j i j ( 8 -- i / / . 'y # L -V p i 4 t - % y % ,, Corporate Energency .J tosponse Center-A Mr$ ~ __ h l T ; $)I l I{Y gN State Police $$ kg? ) teadquarters (804) 323-2300 I e c \- l l '89 a g o f j no$k* . +- L i. i Department of Ibergency Services (DES) l - - + + + p" -a--- - V wg e- g w $' 'NAEE Section 3 Pegs 5 of 5 04-01-85 ~ > \ NEAR3Y ACC E OLATIONS . _,n Richmond (approximately 60 miles from station)- , Boliday Inna 6531 West Broad Street 3 Locations on 804/285-0051 West Broad Street Richmond. VA,* 2000 staples Mill Road 804/359-6061 3200 West Broad Street 804/359-4061 Frederteksburt (approximately 30 miles from station) Ramada Inn Fredericksburg. VA 703/786-8361 Sheraton Inn l-O Fredericksburg VA !V 703/786-8321 i i Charlottesville (approximately 45 minutes fica sta' tion) !- Holiday Inn - North I. Charlottesville. VA = 8,04/293-9111 l Holiday Inn - South l Charlottesville. VA

l. 804/977-5100 Ramada Inn .

l. Charlottesville. VA

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w& s , + i V' % ' 1 - , NAEE S2ctitu 4 Pcg2 1 of 2 04-01-85' SCOPE OF EXERCISE fh . During the week of May 19. 1985. Virginia Power intends to demonstrate its ' capability to effectively implement the North Anna Power Station (NAPS) Emergency Plan. The purpose of this exercise is to activate and evaluate major portions of the Emergency Plan, associated Implementing Procedures, and selected portions of the Virginia Power Corporate Emergency Response Plan in accordance with Nuclear Regulatory Commission Regulation 10CFR50. 47 (b) (14) , and to participate in the implementation of State and local government emergency' response plans as required by the Federal Emergency Management Agency. This exercise will be held in conjunction with small scale emergency response demonstrations by the Commonwealth of Virginia and the Counties of Louisa, Spotsylvania, Orange, Caroline, and Hanover. Simulations of response will be performed with supporting Federal agencies and volunteer groups, as well as other supporting organizations. The exercise shall demonstrate that those- , individuals and agencies who are assigned responsibilities in a radiological I emergency are capable of providing the necessary protective measures to ensure the health and safety of the public in the event of an accident at the NAPS facility. The exercise is intended to initiate responses for all four categories of emergencies as occlined in NUREG-0654. A scenario shall be prepared to accomplish a successive escalation of the emergency from the " Notification of Unusuni Event" to a " General Emergency". Free play is encouraged and controllers will only interfere with the play if the exercise lags behind schedule, if emergency response personnel take incorrect actions to carry them to the next exercise event, or if action 1,s taken that would correct the expected simulated response earlier than scheduled by the scenario. At no time will the exercise be permitted to interfere with the routine safe operation of the station, and station management may, at their discretion, suspend the exercise for any period of time necessary to ensure this goal. Exercise " players" will not have prior knowledge of the simulated incident or ("] any parts thereof. V jmj /SP4/123 ~ NAEE Section.4- : ' i;. ..; 4 Pogs 2 of 2 l 04-01-85 l to, 7 y[ Virginia Power also intends to activate. the Corporate Emergency, Response Plan '( ), . at its General' Of fice Building L-in ~ Richmond, Virginia, to demonstrate: the ; Corporate Emergency Response Center's capability to interact with'the 1,ocal q Emergency Operations Facility at North Anna.

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s 5 ? ? t ..(f ? e t I; p fl jmj /SP4/123 l- 4 p . s.mww.-_u.a.. _ =. . . . m= 4 m_,.4. a-. . %. a a. in*- , a as A , , [ i !! j (- . l 1' i

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). ? I OBJECTIVES 5. 9 e s 1 k 4 e i 'l. - ,_ - - - _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ 2___ NAEEShetien5 , Pego 1 of 6 ; j 04-01-83 , OBJECTIVES OF EXERCISE .f b The objectives of this exercise are to demonstrate by actual performance-a number of key - emergency preparedness functions as they relate to the North Anna Power Station (NAPS) Emergency Plan. The simulated accident will involve response and subsequent recovery actions to include: emergency classification, notification of company personnel and off-site organizations, simulated actions to correct the emergency condition, and initiation of accident assessment and protective actions as necessary to , cope with the event. In addition, the exercise will - simulate an , emergency that results in of f-site radiological releases which require . response by off-site authorities. Simulations of some aspects of . M',m)- emergency preparedness, without actual demonstrations by the Station or g Corporate entities, may occur where it is deemed impractical to call for personnel involvement. The following objectives have been developed in order to establish the. ^ scope of the 1985 NAPS emergency exercise. The objectives ensure ' that -required events are included in the exercise scenario, and establish criteria to be evaluated by controllers and observers during the actual

l. conduct of the exercise.

[ . p l> O 'I jmj/SP4/122

NAEE S ction 5: )

Pegs 2 of 6 04-01-85-- - A. OVERALL STATION OBJECTIVES , Q ,

1. Demonstrate the emergency organization's ability :o make proper decisions related to emergency radiation exposure guidelines,- and the capability to implement these decisions. .

t E 2. Demonstrate at all emergency facilities the ability to establish i and maintain emergency management' command and control authority, and maintain continuity of authority throughout the exercise.

3. Demonstrate the ability to formulate and make protective action recommendations to protect station personnel and the general

-c public based on plant parameters and/or field monitoring information.

4. Demonstrate the ability to classify actual or potential l_ emergencies in accordance with NAPS Emergency Plan Implementing

, lot Procedures with respect to: L l v

a. Notification of Unusual Event

b. Alert

c. Site Area Emergency

d. General Emergency S. Demonstrate the ability to develop alternative systems-:or equipment alterations in response to accident affected. plant systems or components and to formulate respective procedures to accompany these required modifications.

6. Demonstrate the . capability to ascertain and to requisition the necessary parts to perform corrective maintenance on damaged i equipment.

7. Demonstrate the ability . to evacuate non-essential personnel from O the site.

;b jmj /SP4/122 m q

o. .

P NAEE Scction 5 i Pcgo 3 of 6 l 04-01-85 -- L i ? 1 F ,n A. OVERALL STATION OBJECTIVES (continued) ; .l . v.~ ~

8. Simulate transition the recovery 1

] into mode. Requests for simulated technical support will be made. as well as transmitting information to the facilities needed for recovery support.

9. Demonstrate the ability to augment the on-shift emergency organization to support emergency operations in a timely and i effective manner, ,

B. OPERATIONS OBJECTIVES

1. Demonstrate the control room operator's ability to recognize '

operational symptoms indicative of degrading plant conditions.

2. Demonstrate proficiency in evaluating parameters, properly categoriz1ng the situation utilizing- the station's emergency '

,- s action level scheme, and- making the requisite emergency classification.

3. Demonstrate the ability to properly- escalate /de-escalate the emetgency classification.

4. Demonstrate efficient and effective notification / alerting -1 procedures and methods.

p

5. Demonstrate effective communications / informational flow from the control room to supporting locations.

l C. SECURITY OBJECTIVES

1. Demonstrate the adequacy of access control and security for l emergency response facilities.

A; jmj /SP4/122 l ~ *~ NAEE Sccti:n 5' ~ Pego 4 of 6 04-01-85' C. SECURITY OBJECTIVES (continued) -i )- v 2.- Demonstrate station employee accountability.

3. Demonstrate the ability to implement site evacuation and access procedures.-

4. Demonstrate call-out of off-duty station personnel.

5. Demonstrate Security escort capabilities.

D. HEALTH PHYSICS AND CHEMISTRY OBJECTIVES

1. Demonstrate the necessary radiological controls to remove a j contaminated injured individual from an accident scene and to ,j assist the medical team in minimizing the consequences of a i 3 contaminated individual.

1Q - V. 2. Demonstrate. the capability to perform radiological monitoring activities and assessments, and to formulate offsite radiological dose, projections. f

3. Demonstrate the use of the Post Accident Sampling System (within L current existing limitations) . to obtain samples in . support of q

accident assessment activities. This shall- include the sampling ' and analysis of liquids with actual elevated activity levels.

4. Demonstrate collection and analysis of water, vegetation, soil, and air samples both on-site and off-site, as appropriate. !

5. Demonstrate use of communications by the monitoring teams, to include sending, receiving, and understanding message content. ,

6. Demonstrate response to and analysis of simulated elevated ;

' /G airborne and/or liquid activity levels (as appropriate), and of - V) r simulated elevated area radiation levels. jmj/SP4/122

_ __ -_-____ _ -.. _. =

NAEE Sectisn 5' ;. Pcgo 5 cf 6 04-01-85 ~ ~< D. HEALTH PHYSICS AND CHEMISTRY OBJECTIVES (continued) .' / (.,T. /' i

7. Demonstrate initiation and use of appropriate procedures for the collection, analysis, and documentation of Post-Accident and v

Environmental Monitoring samples,- and for Radiological- Monitoring evaluation.

8. Demonstrate the ability to assess data obtained as a result of sampling activities, and the ability to factor results into the ,

overall assessment process. E. HEALTH & SAFETY OBJECTIVES '1. Simulate the injury and contamination of one employee and-demonstrate the following: a) Transportation to an offsite medical facility; and

D' b) Participation by the offsite medical facility.

2. Demonstrate that surrounding Volunteer Rescue Squads can send supporting ' units to the station and simulate successful life support missions in coordination with station personnel assigned to the tasks.

'F'. EMERGENCY RESPONSE FACILITY OBJECTIVES

1. - Demonstrate the staffing of the following Emergency Response Facilities: .

Technical Support Center (TSC) Operational Support Center (OSC) Local Emergency Operations Facility (LEOF) Corporate Emergency Response Center (CERC) O .jmj /SP4 /122 v , v- NAEE Sdeti:n 5: I i Peg 2 6 of 6 ' 04-01-85 N.. - F. EMERGENCY RESPONSE FACILITY OBJECTIVES.(continued)

i' l Af

2. Demonstrate the communications capabilities between the Control Room, TSC, OSC, LEOF, and CERC, and the ability to maintain these communications with Federal, State, and local governments. This shall include sending, receiving, and understanding the content of messages involved.

f

3. Demonstrate the proper utilization of the Emergency Response Facilities and that adequate emergency response equipment exists. -

G. CORPORATE OBJECTIVES

1. Demonstrate that the LEOF can be adequately staffed and communications properly established.

4

2. Demonstrate that the CERC can be - adequately staffed and made fg functional (e.g., maintain communications. interface with the State Emergency Operations personnel at the CERC, provide engineering assistance, provide logistic support, and establish a Rumor Control group).

3. Demonstrate the activation of the Local Media Center.

4. Demonstrate the timely release and distribution of news-announcements.

5. Demonstrate coordination of news announcements with off-site- ;

1 emergency response agencies. . l l l

6. Demonstrate the ability to condttet timely and informative media briefings.

1

7. Demonstrate the ability to respond to outside news inquiries.

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, M X [ Q "f~'l} W 1G: !G W sa.s,, .o . .g l L' -WW +N f__,.'_. *' -,- . . - -. 2I A, 4 -h-e , i m.<? 3 mM'. M.'e'a;m M FW'.a WW. v i.W w 5.,.w,. e .,W.- 4 7 J ed+--a 4'- b W i d---.w.w;.,-e-A.-e---+ 4- - - .. - - - w- . , 6-===-aw.-_.---_-_ - ~ - e +stees == -- T W .c NAEE Scction 6; Pcgs 1 of 3 ' 04-01-85 ; r ~T f VIRGINIA POWER -NORTH ANNA POWER STATION EMERGENCY EXERCISE SCENARIO NARRATIVE i A small scale emergency exercise has been scheduled to be s conducted at the North Anna Power Station during the week of May 19, 1985. Unit I has been designated as the affected unit for the exercise. Unit 1 is operating at 100% of full power equilibrium. The > reactor core is near end of life and reactor coolant fission product inventory is high. Unit 2 is in a refueling shutdown. All fuel has been removed from the reactor and is safely stored in the Spent Fuel Pit. No refueling activities are -being performed i in the Fuel Building. Prior to shutdown, the Unit 2 coolant fission: product activity was elevated resulting in the generation ' of high activity waste gas. This_ gas is presently being stored in one of the waste gas decay tanks. l The. scenario will be initiated by a telephone call to the L North e.nna Security Switchboard. The caller will not identify himself. except to say that he fears nuclear power plants and-is )- g involved in a mission to close them down. He warns of bombs being .t placed in the station and then hangs up and does not call back. It is axpected that the Station Manager and Shift Supervisor .; will be notified of the situation. Security should initiate SPIP 35 and'23 and a " NOTIFICATION OF UNUSUAL EVENT" should be declared in accordance with EPIP-1.01, EAL Tab J.l. Notification of outside agencies involved with bomb detection and disposal, such as the FBI and State Police Explosion Ordinance Division (E0D), will be expected. However, actual calls will be blocked by exercise controllers. A. search for paraphernalia and explosive devices will be organized and conducted by Station Security. A timing device is discovered in the area adjacent to the Fuel Building. -(This lends credibility to the seriousness of the bomb threat). 'Upon further: ' search, a-briefcase-is discovered near.the Unit 1 main generator. Security will recommend local area evacuation and notify the State EOD (call will be blocked) and time will be allotted for the team to arrive. The briefcase will be empty and harmless. Concurrently, one of several available plant maneuvers will be conducted by Operations in response co' the incident. Because it is not certain what method the Shift Supe rvisor or Station Emergency Manager will use to place the plant in a safe 1/~'v configuration, several options will be presented by the exercise , controller. These are:

1. Reenin at power.

NAEE Scction 6 Pcg2 2 of 3 04-02-85 - ' !o _L , VL 2. Conduct a normal shutdown at 0.3% per minute followed by boration and normal cooldown.

3. Conduct a 5% per minute shutdown followed by boration and normal cooldown.

In time, an " ALERT" will be declared in accordance with EAL Tab K.6, "Ex plosiv e Damage To Facility", when a bomb explodes in the "A" Waste Gas Decay Tank area. ( T his information fa in the form of a controlled message to the C ontrol Room Shift Supervisor). No fire or personnel injury will occur. 1 r An unisolable radioactive gas leak from the Waste Gas Decay. Tank starts and is detected by radiation alarms in the Fuel B uildin g 'and D econtamination B uildin g - Radiation Monitorin g Instru me ntation. Local area radiation monitors also increase due to the laak. A P-5 (Radiation Monitorin g) shall be initiated in response to this EV EN T. - Eventually a " SIT E AREA EM E R G E N C Y" will be declared in accordance L with E AL Tab E. Radiation pvels in the ventilation ~ [

system "B" stack will exceed 8.0 x 10 M R/H R in coincidence with Vent Vent ' gaseous monitor off-scale "high" as the leak from

" A" W G D T continues. n .- During the exercise, a member of an Onsite Health Physics l Monitorin g Team will fall and . receive injuries w hile p erformin g - his monitoring d uties. He will be able. to notify supervision of his problem and location. Management will coordinate efforts to ' locate .the' individual and provide first aid. A local rescue squad 4 will participate in the recovery and transportation of the individual to the Medical. College of Virginia. ' T he victim will b e considered to be contaminated. 1. Another bomb will then explode, rupturing the second Warte , L Gas Decay Tank. T his leak cannot be isolated and radiation .v L levels increase in the ventilation vent stack " B". Eventually , Vent Vent "B" radiation levels exceed 3.2 x 10 MR/HR and Health Physics assessment at the site boundary p roject greater-

L than 2 REM w hole body or 12 REM ' thyroid exposure. A
l. "GENER AL LMERG EN CY" is declared in accordance with EAL Tab B.

, Radioactive gas will continue to be release d to the , ,; atmosphere via the vent stack until both vaste gas decay tanks ; d ep ressurize. At this time, the release will be terminated. A recovery from the incident will be initiated and .. de-escalation of the emergency will follow. r v) A l NAEE Scction 6 E" ' Pcgo 3 of 3 04-01-85 l i y ("~N l l ) 'L/ The exercise will be terminated af ter recovery actions are complete and a critique of the exercise vill be conducted in the North Anna Training Facility, i 0 j i 4 ) -)u] ; b i e . l i i f ( - Ls. . + e q I Y i ) i t 9 9 % u i e l i % . n NAEE Scction 7 yv' , Paga 1 cf 2 04-01-85 4 *- i VIRGINIA POWER f1J s.~ NORTH ANNA POWER STATION 1985 EMERGENCY EXERCISE SCENARIO WEEK OF MAY 19, 1985 NOTE: TIMES ARE APPROXIMATE TIME EVENT p b 0600 --Exercise begins: The Shift Supervisor has been notified that a-bomb threat was received by Station Security. - A " Notification of Unusual Event" is declared (EAL Tab J.1.). - SPIP-35 is initiated and_a search for the explosive device begins. 0700 - IRPI P-10 is returned to service and tested satisfactorily. i 0830 - A bomb explodes in the Waste Gas Decay Tank Area. - An " Alert" is declared (EAL Tab K.6.). -[Y - Initiate Plant Shutdqwn. 1b- - Radioactive gan begins leaking from "A" Waste Gas Decay Tani. f t -2 ? 1030 - Vent Stack "B" Radiation Levels exceed 8.0 x 10 mR/Hr. ! e - A " Site Area Emergency" is declarod-(EAL Tab E.4.c.). . p 14 1100 - An Onsite Health Physics Monitoring Team Member ]_ n is injured while perfor;ning his duties. The individual is contaminated and must be transported to an offsite medical

facility for treatment.

1200 "B" Waste Gas Decay Tank ruptures.. f p j 1205 - Vent Stack "B" Radiation Levels exceed 3.2 x 10 -1 mR/Hr or y l' Dose Rates at Site Boundary exceed 2R Whole Body (12R Thyroid). .; L - - A " General Emergency" is declared - (EAL Tab E. 5.b.3) . i , 1345 - Both Waste Gas Decay Tanks are now empty. lb - The release is terminated. ' i \ ? r l L i l

i i

- u ' ~ 3.0 EMfitGENCY OPERAIlONS TACILIIY_(f0f) OllSEPVER Site __ Observer fate of Exercise - _ _ - . STANDARDS EXPECTED LICENSEE RESPONSE ^EIII^l lIIENSf f NISP0i3Sf/ C0t W ilIS 3.1 Activationrof EOF - 3.1.1 Functions for Site Area and General Emergencies - the EOF is activated and prepared to perform the following func-tions within about I hour , efter the emergency is dectared: , 3.1.1.1 k nage corporate esergency resources. (Prior to acti-vation.of the ECF, this may have been initated at the TSC.) 3.1.1.2 & nage radiological etfluent and environs monitoring and , dose projections. (Prior to activation of the EOF, this may have been initated at the TSC.) 3.1.1. 3 Notify Federal, State, and local emergency response organizations of the emer-gency and make recommen-dations for public protective action. (Prior to activation , of the EOF, this may have been initated at the TSC.) 3,3 .s EMfRGENCY OPERAIlf 3 FACl QIY,(f0f) OllSERVER Site , _fObserver 11 ate of Exercise . STANDARDS EXPECTfD LICENSEE RESPONSE ACIllAL LiffMsfi lif SPONSf/ CotWHIS 3.1.1.4 Establish and maintain a - primary coamunication link - with the TSC. 3.1.1.5 Interface with NRC Site Team. 3.1.2 Personnel The following personnel are prepared to implement their appropriate functions at the , EOF within the time frames specified in Table 8-1 of NUREG-0654 or the site emergency plans or procedures atter the emergency is declared: 3.1.2.1 An EOF Director. 3.1.2'2 An appropriat- ealth physics expert to pe- ora offsite dose asse: ,t (may be stationed a the TSC or EOF). 3.1.2.3 Qualified statf members to maintain notifications and communications (will be stationed at the T5C and EDF). s 3.2 - _ - - . _ _ ~ _ - _ _ . - _ _ . . -- EMfRGfNCY OPERAIlfC6 FACILI fY (f0f) OltSEPVER Site Dbserver Date of Exercise STANDARDS EXPECTED LICENSEE RESPONSE AL E MWNW 3.1.2.4 Staff members capable of . . performing of(site surveys - and capable of performing onsite (out-of plant) surveys (may report to EOF or survey te.sm). , . 3.1.2.5 Health physics technicians . for radiation protection. In addition-3.1.2.6 Personnel are not pre-positioned prior to the commencement of the exercise. 3.1.2.7 Ine personnel performing key functions are those assigned on the duty roster and are knowledgeable in their duties and responsibilities. p 3.2 Of fsite Dose Assessment (See IE inspection procedure 82207.) 3.2.1 If a release is anticipated or ongoing, correctly assess and integrate information from reactor systems status and trends, radiological monitoring, source ters assumptions, and meteoro-logical information to define 3.3 the m.gnitude and area-ef the offsite impact. , 9 EMfitGENCY OPfilAll0NS FACit._tlY (fpf) OnifPVER Site Observer __ Date of Exercise STANDAkDS EXPECIfD LICENSEE RESPONSE A THAL Rf WONSf/ 3.2.2 If a release is anticipated . or ongoing, deploy initial environmental sampling team (s) to appropriate locations to intercept plume; direct team (s) regarding geographical movemenL (e.g., remain at predesignated location, go to appropriate center, begin traverse from location to location). , 3.2.3 Direct team (s) regarding measurements or samples to pe taken (e.g. , gross p/y, air sample, water sample, vege-tation, milk. TLDs). 3.2.4 use results of monitoring to ' redefine the source term and projected doses, as appropriate. 3.2.5 If a release is under way, promptly and correctly project the direction and maximum dose within the plume EPZ and the distance to which the EPA's PAGs are projected to be exceeded. 5 3.4 + EMfRg NCY OPERATIONS FACILilY (f0f}__0ttsfpVER Site Observer Date of Exercise . STANDARDS EXPECTED LICENSEE RESPONSE ^ "#I LIf.fMWF HE.WNSf/ CoffifMIS 3.2.6 Interact with reactor system's ," status personnel to comprehend plant status and' trends-anticipate radiological consequences of progression of events. - 5, 2. 7 Obtain necessary current and forecasted meteorological ~ information from onsite . systems and appropriate - offsite sources (e.g., supplemental systems, National Weather Service). 2.2.0 Assure assessments are - updated as tangible changes in plant status, release, or meteorological conditions are evident, are forecasted, or ire refined from confirmatory measurements. !3.2.9 Proper procedures are used for dose assessment and per- ' sonnel know how to use them. k 3.5 ~ , EMrRr4NCY OPERATIONS FACILIIY jfor) Of5fRVER Site Observer Date of Exercise STANDAHDS EXPECIFD LICENSEE RESPf4SE A NI' II 3.3 Protective Action Decisionmaking . (See IE inspection procedure . 82202.) ~ 3.3.1 As appropriate, use EALs to decide on protective actions . for offsite personnel without Wditing for a dose assessment. (Prior to activation of the EOF, this may have been ini-tiated at the TSC.) . 3.3.2 Promptly recommeno protective . actions offsite that are consistent with those in EPA's PAG Manual for those l conditions not involving core melt. . 3.3.3 Within 15 minutes of the - operator's declaration of ' General Emergency Conditions l and if the EOF is staffed and - functional, recommend appro- - priate protective actions to offsite officials. At a minimum, this should include sheltering in an area of a . 2-mile radius and 5 miles down wind. The recommen-dation may also include evacuation of parts of the

EPZ if the General Emergency involves a core melt: 3.6

~- , . _ v .,. , EMfRGENCY_ OPERA 110NSFACilllYjf00)OH5fPVER Site Dite of Exercise Observer _ _ ^U "Al b STANDARDS EXPECTfD LICENSEE RESPONSE kI For core melt sequences , where significant releases from containment are not yet taking place and . large amounts of fission products are not yet in the containment atmosphere, consider 2 mile pre-cautionary evacuation. Consider 5 mile downwind evacuation (45' to 90* - sector) if large amounts

of fission products l (greater than gap activity) dre in the Containment atmosphere. Recommend sheltering in other parts of the plume exposure EPZ under this circumstance.

O e 3.7 - m i . EMIRGENCYOPERATIONSFACILITYjr0F)OttSFPVER { - - l Site Observen- Date of Exercise w STANDARDS EXPECTED LICENSEE RESPONSE ACillAL LICfMSI f RfSPONSE/ C0ffi[ MIS For core melt sequences . l where significant releases - from containment are not yet taking place and-containment failure leading to,a direct l atmospheric release is I likely in the sequence , but not imminent and large amounts of fission - ! products in addition to l noble gases are in the i containment atmosphere m consider precautionary evacuation in a S-mile - radius and 10 miles downwind (45* to 90* sector). For core melt sequences , where large amounts of fission products other 7 than noble gases are in , the containment atmosphere I and containment failyre is judged ime,inent, f recommend shelter for those areas where evacuation cannot be completed before transport of . activity to that location. 1 s 3.3 . . _ _ . ~ . - . . _ . EMfRr.ENCYG?ERATIONSFACILITYJfDF)OH5fPVER ,, Site ~0bserver flate of Exercise I STANDARDS EXPECTED LICENSEE RESPONSE Ar. MAL RESPONSE / i ._ 3.3.4 Consider at least the following ~ parameters in deciding upon

appropriate protective actions:

current reactor status prognosis of accident expected duration of release / , evacuation time estimates ' local sheltering efficiencies current and projected weather conditions . local geography - time of day 3.3.5 Recommend evacuation of an - ~ area of a 2-mile radius if physical control of the facility is lost. . 5 3.9 ~- _. - . _ ___ - _ - ___, ~ _. - l - emf RGENCY OPERATIONS ___F_A.CI.L._I_T.Y E0f) OHSEP.VEP ~

Site Observer _

Date of Exercise . STANDARDS EXPECTED LICENSEE RESPONSE ACTUAL LICfMSff RfSPONSF/ CfM ENTS ~ I 3.3.6 Recommend KI for offsite

emergency workers if iodine doses in excess of EPA thyroid PAGs are projected. g 3.3 7 If a release is under way or anticipated, recommend appro-f priate actions (e.g., advance ,

deployment of environmental monitoring teams, change in classification, or taking . protective actions). i 3.3.8 Correctly convey results of assessment, bases to support assessment and forecast con-ditions to management and make recommendations regardir:g appropriate actions and ~ . options. 3.4 Notifications (See IE inspection procedure 82203.) 3.4.1 Set up a communications channel to offsite authoritie.s. including NRC. k 3.10 4 .- * . -v-- , , w2 %.. ,w. . w, EWRG.E.NC.Y. OP.E.R. AT IONS FACILITY _(f0f]_OltSEPVER . Site Observer _ pate of Exercise . r STANDARDS -l EXPECTfD LICENSEE RESPONSE ACillAL LICENSIT HISI'ONSF/ cggys 3.4.2 If not already done so by the . TSC or the control room, promptly inform offsite officials (including NRC) of: emergency conditions emergency classification radioactivity release [ ~ status j ~ potentially affected population projected population doses recommended protective actions any changes in these conditions 3.4.3 Maintain communications with the offsite authorities.

3. 5 - Implementation of Protective Actions (See IE inspection procedure 82202.)

3.5.1 Confirm and periodically ' assess the habitability of 3'gl the EOF. - _ . . _ .n. , . . . ~ . . EMfRGENCY OPERA MONS FACILITY (ref) O_ltS__E.RVER -_ Site Observer _ _ , Date of Exercise _. - - . . i STANDARDS EXPECTFD LICENSEE RESPONSE ACIllAL LiffMsli HiSPONSI/ CotW HIS 3.5.2 If EOF evacuation is required, . the functions are transferred i to alternate facilities without disruption of offsite interface, command and control, dose projections, or

protective action decision-making.

3.5.3 The licensee confirms that offsite authorities are aware ' of the licensee's recommenda-tions for protective . actions. l l 3.5.4 The licensee determines froci the offsite authorities what, ! if any, protective actions I are being taken, and informs l , management and NRC. g I The licensee maintains 3.5.5 , cognizance of status of l offsite protective actions. l i I i ! i ? *) f l 3.12 ., ...a . .- - . - , . , , . , . EMfHGfNCY p'ERATIONS_ FACit.11Y __(f00) OH,5fPVER Site Observer Date of Exercise .- . . _ _. STANDARDS EXPECITD LICENSEE RESPONSE AClllAL LiffMSIT RISPONSF/ CottfMTS 3.0 Interface with Offsite Officials _ , 3.6.1 Offsite. representatives at the EOF ad the site are I briefed upon arrival and kept informed on ch'anging conditions without interfering with onsite response. 9 3.6.2 Offsite. monitoring and . sampling results are coor- . dinated with offsite officials,

3. 7 General .

3.7.1 The controllers do not prompt. I , coach, or otherwise interfere with the exercise of this . center / team. - 3.7.2 Plant procedures are available and are up to date. 3.7.3 Correct procedures are used. 3.7.4 The personnel performing key - functions'are those assigned on the duty roster and are knowledgeable in their duties and responsibilities. S 3.13 W v . w r , .z ~ EMFRRteCYOPERAIIONSFACILiIYjF0F)OllSEPVER Site Observer _ , Date of Exercise STANDARDS EXIECTfD LICENSEE RESPONSE ^ f' 5U l 3.7.5 EOF personnel interaction is

frequent and proper with each [

other and with other centers l (especially with corporate , headquarters and with offsite !, I-authorities). - l I 3.7.6 Congestion and noise level ) are kept to a minimum.

3. 7. 7 All primary c - mications -

systems function properly and if not, backup systems are dVailable. 3.7.8 Proper functions are transferred to tne EOF in a timely manner when'it becomes operational. , 3.7.9 ,All concerned parties are -notified of such transfer. 3.7.10 Bound logs are kept and all important data, calculations, notifications, and decisions are recorded chronologically. 3.7.11 Relief personnel were properly and adequately briefed by the personnel tiiey were relieving. 3.14 _,.-m.s,,, , - , . . , ..~ _- ._._.__.,,._..__# .. - . - , , , _ _ ,_______m_,h, e' - EMrtirrMCYOPfpilONSFACILITY.jf0f)OftS7PVER Site Observer Date of Exercise . l - STANDARDS E?.FECTfD LICENSEE RESPONSF AU"^l I' "I 'II i l 3 l 3.7.12 The EOF is properly equipped to ' ~ perform its functions. . 3.7.'13 Job aids such as status boards are accurate and are kept up to date. 3.7. 14 At the request of the TSC, control room, or others, outside resources are obtained in a timely manner. . I 9 i ~ a ~. . j I 1 I 3.15 \ ----... -- ., , m , . _.m_, ,..,_.m.,,,.,_ m_____m ..m _,________.___....-.m_i., m , NAEE Sectitn 7 , Pcg3 2 of 2 i 04-01-85 ! l 1 r, ; ,'-~ . 5 .i'- i ny m ; i i i 1400 - Recovery Phase is initiated. ! 1500- - Exercise terminates. l I 1 .1 I [ , N b l' f r i a l-l a t 9 9 7 Q,-p0g3g.o Vi ajMv ie.. m' ' ,> ;+'!ag s gvu aL + - *. . . . R: @ , w sc -y m 3 r v, ~i c 1- c ..; e e u m _ c' , j.pf# ,. 4M c m, ",q ; g ~ ..v.M U. i , s !' d' 't

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(- , NAEE S*:ction 8 s Paga 1 ef 1 04-01-85 . _ . VIRGINIA ELECTRIC AND POWER COMPANY l ( 'i NORTH ANNA EMERGENCY EXERCI5E A_) t LIST OF PARTICIPANTS l The following organizations, agencies, and political subdivisions will participate in the North Anna Power Station Emergency Exercise: i A. Virginia Power

1. Corporate Headquarters (804) 771-3000 j

2. North SAnna Power Station (NAPS) (703) 894-5151

3. North Anna Power Station News Media Center (703) 894-4826/4662 B. State Agencies, Commonwealth of Virginia i

1. Emergency Services, Department of (804) 323-2300 f

2. Health, Department of (804) 323-2300 (State EOC)

3. State Polic1, Department of (804) 323-2014/2000 !

.r3 , kJ 4. Other Stato agenciost for moro details. See Vopex 1-85, Administrative lustructiona ' . C. Local Gavernments :

1. Carolins County (604) 633-00J1 I, . . ,

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2. Hanover County (804) 798-6081 Ext. 217 .

3. Louisa County (703) 967-0401 I

4. Orange County (703) 672-3313

5. Spotsylvania County (703) 582-5676/6384 ,

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I i I

)' VIRGINIA POWER NORTH ANNA POWER STATION j 1985 DERGENCY EXERCISE INITIAL CONDITIONS I SHIFT SUPERVISOR l OPERATIONS SUPCRINTENDENT j STATION MANAGER ! 1 NOTE: This drill affects systems common to both units. NOTE: If at any time, in the judgement of the Shift Supervisor, the i Emergency Drill interferes with the safe operation of the unit. I the drill will be suspended until station conditions are returned j to normal. PLANT CONDITIONS ! I. Reactor + A. Unit " is in a b.lueling Outage - all fuea is in the Spont Fuel }.g) Pit - this unit has had a history of fuel failure. No fuel ; movement is in p.* ogress.

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Ooolant activity at time of chutdown : 2.65 utih 1 0.r. :-131 L. Unit 1 is at 100% power (equilibrium) - thio unit also has a fuel failure proolem. Coolant activity 0.90 uci/ml D.E. 7-131 C. Burn-up Unit 1: 9975 MWD /MTV D. 399 PPM Boron E. "D" Control bank at 228 steps II Maintenance A. Component Cooling Pump "A" (2-CC-P-1A) OOC - tagged out due to seal leaks. Seals have been replaced; however, the motor has not 1 been recoupled. No work is in progress. B. Instrument technicians are calibrating the Rod Position Indication for Rod P-10 on Unit 1. 11 steps out. 1-FW-P-3A is tagged out for periodic maintenance. C. No other major maintenance proj ects are being conducted. All k other equiptent is as per the "Turnever Check List". ~ NAEE S:ctin 9 Pcge 2 cf 2 04-01-85 l III. Radioactive Releases k'~) A. Liquid waste is being processed via the Chem Nuc. !X, Clarifier and Clarifier Ion Exchanger. The "A" Low Level Tank level is 93% - paperwork has been submitted to Hetith Physics for release. The "B" tow Level Tank level is 50% and filling. B. No gaseous releases are in progress except for normal flow via "A" and "B" stacks. Pressure in the "A" Wasta Gas Decay Tank is 125 PSIG and paperwork has been submitted for release. Pressure in the "B" Waste Gas Decay Tank is 60 PSIG. 1-BR-64 leaks thru slowly. IV. System Line Up and Flow Paths A. Normal charging and letdown: 1-CH-P-1B running. Letdown flow g 125 GPM to allow faster clean up of the RCS. . B. All Main Steam PORV's, S t eam Dumps . Decay Heat Release Valves, and Safeties are operable. C. Pressurizer PORV's and Safeties are operable with Block HVV's open, j D. Station Servica, Peserve, and Emergency Busses are operable. The [' 2H dieal is disassessbled fer a rebuild. 1H, 1J and 2J Mesels are in auccmatic. ' i V. Ventilation . A. Vent stack "A" flow is g 68,000 CFM. 2 Central and 2 General fans are in service. B. Vent stack "B" flow is % 65,000 Cm. 2 Fuel Building, 1 Decon Building, and 2 Safeguards exhaust fans are in service. C. Charcoal todine filter system is operable, but not in sernce. VI. Miscellaneous A. Due to a drainage problem, the lower level of the Decon Building is contaminated and reads 20,000 to 30,000 cpm smearable. , e i , r aym c. .i .- n s<< %s J r., j N a t I ..- m 2 .- ',

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CASEOUS PFCt* RI.DG FAFTICt*a. ATE GASEtWS REW FtTL AREA FUFL FIT (CFM) (CFM) (MR/RR) (CFM) (f?M) AREA (R/IIR) (CFM) (CrH) RRIDGE (R/prR)

(R/NR) TIME RM-V& ll2 RM-VC-II) RM-RMS-IF5 RM-VG-105 RM-VC-606 RM-R W ISI RM-VG-lOS W TC-IO6 RM-RMS-152 RM-RMS-153 1830 3F+6 OFFSCALE .044 0FTSCALE OFFSCALE 3 E-3 2E*4 2E*4 IF-3 9E-4 1845 1.5E*6 OFFSCALE .026 0FFSCALE OFTSCAIE 2 E-3 2E+4 2E+4 8E-4 TE-4 1200 IF+6 OFFSCALE .34 0FFSCALE OFFSCALE 2 E- 3 2E*4 2E*4 IIE 4 7F-4 1215 OFFSCALE OFFSCAI.E .31 OFFSCALE OFFSCAI.E I E .? 2E L 2F*4 2.2E-3 1.SF-3 1230 JE*6 0FFSCALF. .036 CFFSGALE OFFSCALF 3 F-3 2E*4 2E*4 IE-3 9E-4 1745 IF*6 0FFSCALE .02 0FFSCAl.E OFFSCALE 2 E-3 2E+4 2E+4 SE-4 6F-4 1300 4E*5 6E+6 .02 0FFSCALE OFFSCALE I.5E-3 2E*4 2E+4 7E.4 $g g 3315 IE+5 IE+5 .02 SE*5 3E+5 1.2E-1 '2E*4 IE+4 6E-6 5F-4 1330 4E+4 IE+4 .02 I.5E45 9E 4 1.2E-3 6F*3 4E*3 6E-4 SE-4 1345 3.5E*4 IE*4 .02 5E*4 3E+4 !.2E-3 3E*3 2E*3 6E-4 SE-4 1400 7F+1 AE*3 .02 2E+4 IE+4 1.2E-3 IF*3 TE+3 6F-4 $E-4 Oe= 2* b > 9 to M OeM 9 69 tf3 CD e Vs C f) M et M. WO M3 to s.* O n' .,.n. -- n -- y'M.'s l' ,s +r -',y't ^ S 1 y (- ;J . . ..- --( 1 y 4 f 4 m 4 ,( . ggg't. . 4, ..m ,- f m - y y.) ' s NAEE SectionT10i id@ ~ ndY f V - Pags 4'ofL172f 47NSFM ' m}p%g , , 01-85: .. he.n k .: QWL.s. .t 3 3, o, r s y yc p :g w~. p

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p ' fjg] y g7 ' ,o. . METEROLOGICAL DATA g% f sg. w , . :::v , ~ v, r ,> , a; . @. 1, , ; : DELTA 'T =. -0.69 m,- s , w s. w c ' ~ . SIGMA.. THETA =1 10.O-Jiti , ;W < . [ WIND ' DIRECTION. ?-(from) - NNE, 23' - - .s ? ,%, , :(to)! "iSSW, 203 , I h ' ', . I* 'L' A ?!b4 [' " , M ' , , f ' WIND SPEED.= '5.0 mph 1 'k ) . f Ett 2 t ~ y i. e f n i I % L f I a g 4

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) ? hc. ' 4 =, ,s ,\. .,. ' I ; 3 'I } " Y. 2 ' ~ . l {: u . ?.- -, '.h li ' s' F.' e!* l g - l.f,w .e.Q , i

s. . : i; s

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3 v'.. .' t 3

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~~a. m. a. w . a. w.~~

. . a. e. m. =* W N 2 C E 5 * * * " " = s saw a*SE S*E Q33dS QN M 88* !!AEE Saction- 10.' - Pegs 6 of 172-04-01-85 ?'^'N{ r ? N- "j " . RCS ACTIVITY - UNIT 2 . -f NUCLIDE EQUIVALENT ACTIVITY 4 .i I-131 1.85 E + 0 , s I-132 8.02 E - 3 I-133 7.09 E - 1 , I-134 1.30 E - 3 I-135 7.84 E - 2 2.65 E + 0 uC1/mi' D.E. I-131 XE - 133 2.12 E + 2 , .)CE - 133M 2.15 E + 0 XE - 135 2.57 E'+ 1 I jo,'%[. , }s,,) XE .135M. 1.39 E + 0 l XE - 138 1,29 E + 1 L 1 2.54 E + 2 uC1/mi D.E. XE-133' V .t

t. ?

$ :l RCS ACTIVITY - UNIT 1 1 Mut11 ply above numbers by: .374 l-I l' a I.- o> \ . %.J

t.

~~NAEE'Socti:n'10 Pcg3-7 of 172~~

~~04-01-85~~

.~., 7- ~ x i 4 . < ,i , PLANT STATUS- , E NORTH ANNA POWER STATION j 1985 EMERGENCY EXERCISE b t PLANT MANEUVER OPTION NO. 1 S/D - 100% To 0%, 50 F/Hr Cooldown > (0.3% per minute) j Normal Shutdown from 100% power to Zero power at 0.3% - per minute ( 150 Megawatts per hour), followed by emergency i boration to Cold Shutdown concentration. 2200 gallons of Boron will be required at a flow = rate of 50 gallons per minute. 44 minutes will be required for injection and an. ! fr-4( additional 30 minutes for mixing and sampling. 1, A Cooldown will commence at the rate of 50fF per hour for the following three hours. It is expected that all applicable procedures will be used to accomplish the Shutdown, Boration and Cooldown. . 1i l :' h' ( PLANT STATUS [g[fo*f$h l NORTH Al@eA POwtR STATION 04-01-85 UNIT 940 Mw M atm.a ort cu 1 , -IMARY -SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH618. ac F HOTTEST TC 5 591*F LOOP5 1 AT 59.7 F LOOP *2 AT 59.7 F LOOP #3 AT 59.7 0F PRESSURE 2233.8 PSIG PRES $URIZER LEVEL o % PRT LEVEL se % REACTORCOOLANTfUMP As A. / R. , 00C 3: A. @ 00C C: A. @ 00C CORE PARAMETERS h .. .. .. CORE EXIT THERMOCOUPLE 632 *F _ , , . . MARGIN TO SATURATION Ch A - n *F Ch 8 - ,, 'F ,, . .; . .. SOURCE RANGE. COUNTS N 31 - off N 32 - erf ~ -4 . . .. _... INTERMEDIATE. RANGE AMPS N 3S - s x 10 N 36 - 3 x lo'4 ~ RVLIS 100 % ,_ , ,, ,,_,_ , CONTAINMENT 97 oF PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP. ... CONT. ISOLATION PHASE I. II. III: HYOROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 44 % B 44 % C 44 % , AUX. FEE 0 WATER AUX. FEED FLOW o (GPM) CN-TK-l/2 LEVEL 99 % h - 3As A. R. 38: (JD R. 00C FW-P-2 Q R. 00C h ENGINEERED SAFEGUARDS - RWST 99 % SIFLOW o B:@ R. 00C (GPM) $k HHSI As A.@ 00C. 85 @ R. 00C C ($ R. 00C OSRS A: (3') R. 00C . LHSI As(O R. 00C .B: (0 R. 00C ISRS AsW R. 00C B: dQ R'. 00C 0S As/O R. 00C B (W) R. 00C RS-P-3A: (d) R. 00C RS-P-3B: (O R. 00C ~ RS-TK-1: 97 % ELECTRICAL DISTRIBUTION E GENCY BUS (SUPPLY) DEAD BACKFEED H:RS DIESEL. DEAD BACKFEED EMERGENCY DIESEL GENERATOR (EDG) h DIESEL. H OP. h .00C J: OP.h. 00C RESERVE STATION SERVICE . As @ 0EAQ. B @ /0EAD , Ch/0EAD. HIGH RANGE EFFLUENT RAD HONITORS -VENT VENT . PROCESS VENT MAIN STEAM A B C REMARKS Comence Shutdown . 9erated 12 ca!!cns. .. 9 o.3% / min. or 150 MW/HR. Bank "D" Rods at 228 Steps _ LEGENO:- HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY I LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Ave 11mble. R = Running. 00C = Out of Commission) "R*f ndE*SPV N*nf hAadha 111 % Q.a f h. . . _ NAEE Section 10 PLANT STATUS Page 9 of 172 04-oi-85 " 1/4 NORTH ANNA POWER STAT]CN 922 m NN NCN 1 REACTOR POWER 97.s % GRIMARYSYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 619.f F HOTTEST TCs62.4 'F LOOP *1 AT 59 7 F LOOP "2 AT 59.7 F LOOP "3 AT 59.i CF PRESSURE 2224 PSIG PRESSURIZER LEVEL se % PRT LEVEL sa % J REACTOR C00LAN UMP ; A A. R. 00C B: A. @ 00C C: A. b 00C CORE PARAMETERS .. CORE EXIT THERMOCOUPLE 629 *F .. MARGIN TO . SATURATION Ch A - 29 *F Ch 8 - 29 *F SOURCE RANGE COUNTS N 31 - off N 32 - eff _, ~4 ~4 . .. INTERMEDIATE.. RANGE. AMPS N 35 - 5 x 1o N 36 - 3x 10 ~ RVLIS 3no % 97 F 99 PSIA SUMP LEVEL 40 % TEMP. PRESS. CONT. ISOLATION PHASE I. II. III: HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEU - A 44 %B 44 % C 44 % AUX. FEEDWATER AUX. FEED FLOW n (GPM) CN-TK-1/2 LEVEL 99 % O 3As A. R. M 38: $ R. 00C FV-P-2 /Q R. 00C ENGINEERED SAFEGUARDS - RWST 99 % SI FLOW o (GPM) ~ HHSI As A. @ 00C. B: @ R. 00C C @ R.00C OSRS As @ R. 00C B /2V R. 00C LHSI As @ R. 00C B: @ R. 00C ISRS As /0 R. 00C B: @ R.'00C OS As/O R. 00C B:/4, R. 00C RS-P-3A (S R. 00C '~ ~ RS-P-38: (@, R. 00C . RS-TK-1: 97 % ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) @ DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) h DIESEL. DEAD. BACKFEED H:OP h .00C J: OP .00C RESERV STATION SERVICE . As T DEAD B:M OEAD CadIOT) DEAD. p HIGH RANGE EFFLUENT RAD MONITORS VENT VENT. _ PROCESS VENT MAIN STEAM. A B C REMARKS s ae.k "o" ocas at 21s seers O .. LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eble. R : Running. 00C = Out of Comg _ _ gy gyg7g NAEE Section 10 Page 10 of 17 . g," PORTH ANNA POWER STATION 04-01-85 WIT 1 ese a miruvra or:Ier: 1 , CIMARY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 613 'F HOTTEST TC 559.B'F LOOP'1 AT 53.2 *F toop e2 AT su *F LOOP "3 AT su 'F PRESSURE 2239 PSIG PRESSURIZER LEVEL so % PRT LEVEL se % REACTOR C00LAN UMP A: A. 00C g A. h 00C C: A. N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE s21 *F ' MARGIN ..TO . SATURATION Ch A . 36 *F Ch 3 - 36 *p .. SOURCE . RANGE.. COUNTS N 31 - off N 32 - off ~ ~4 . INTERMEDIATE.. RANGE AMPS N 35 - 5 x 10 ' N 36 - 3 x 10 ~~ RVLIS 100 % . . . . . . . . . . . . . _ _ . . . . . F o_o PSIA SUMP LEVEL 40 % TEMP. 97 PRESS. CONT. ISOLATION PHASE I. II. III: HYOROGEN % _ SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 44 %B 44 % C 44 % A .. AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % O' AUX. 3As FEE A. R.0 WATER 3B: h R. 00C FV-P-2 (I) R. 00C ENGINEERED SAF GUARDS - RWST 99 % SIFLOW o (GPM) HHSI As A. 00C B: $ R. 00C C (@ R. 00C OSRS As @ R. 00C B:(1Q R. 00C ~ . LHSI A lid R. 00C B: (4) R. 00C ISRS As Gb/ R. 00C B:(D R. 00C OS. A:8) R. 00C B: (O R. 00C RS-P-3A (Q R. 00C ' ' - ' ~ ~ RS-P-38: CA) R. 0 0 C RS-TK-1: 97 % . ELECTRICAL OISTRIBUTION NCY BUS (SUPPLY) OIESEL. DEAD BACKFEED DEAD. BACKFEED E RS RGENCY DIESEL GENERATOR (EOG) @ DIESEL H:OP. @ 00C J: OP@,00C RESERVE STATION SERVICE ~ AsdidDOEAO_ __ B:(TOD'OEAD C M OEAO HIGH RANGE EFFLUENT RA0 HONITORS . VENT VENT ,, PROCESS VENT MAIN STEAM A B C MARKS te s! ce no cati

n sers a an # n es u 4 cs- i = e o-o LEGENO:' HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS .- RESERVE STATION SERVICE (A : Ave 21able. R : Running. 00C = Out of Commission) _

PLANT STATUS NORTH AletA POWER STCaTICH , e2s xw RY SYSTEM REACTOR COOLANT SYSTEM l PRESSURE 2227 PRT LEVEL REACTOR COOLANT PUMP A: A. N SOURCE RANGE. COUNTS N 31 - R IS 97 F PRESS. 9.9 TEMP. HYDROGEN . CONT. SECONDARY SYSTEM STEAM A 44 l AUX. FEEDWATER 3As- A. R. ENGINEERED SAJF GUARDS RS-P-38: /@ R. 00C . .. ELECTRICAL DISTRIBUTION EM RS DIESEL. DEAD. BACKFEED @DEAtl. l PROCESS VENT MAIN STEAM Bank "D" Rods at 189 Stecs LEGEND: PLANT STATUS ~ '78 NAEE Section 10 Page 11 of 172 , 04 01-85 , , UNIT 1 MANEUVER CPTICN l_ , (T = Temperature)- HOTTEST TH 609.PF HOTTEST TC558 3 *F l LOOP *1 AT 91.s *F Loop .2 AT 51.5 F LOOP "3 AT 51.5 CF { PSIG PRESSURIZER LEVEL 61 % 6B % 00C 3 A. /D 00C C: A. N 00C CORE PARAMETERS CORF. EXIT . THERMOCOUPLE 617.5 'F MARGIN TQ_. SATURATION Ch A - 3a *F Ch 9 - 38 'F ,, eff N 32 - eff _, ~4 .. INTERMEDIATE.8ANGE. AMPS N 35 - 4.5 x 10 N 36 - 2.e x 10 _ 4m % ,, ,_ , , ,_ _ _ ,,,, ,,_ , , , , , , , PSIA SUMP LEVEL 40 % % I ISOLATION PHASE !. II. III: GENERATOR (LEVEL) % B 44 % C 44 % AUX. FEED FLOW n (GPM) CN-TK-1/2 LEVEL 99 % 38 ,@ R. 00C FW-P-2 $ R. 00C 99 % SIFLOW o (GPM) - RWST HHSI As A.G/ 00C B: @ R. 00C C: @ R. 00C OSRS As dD R. 00C B:/O R. 00C LHS! A 19 R. 00C B: @ R. 00C ISRS As 'dlI) R. '00C B:[fDR.00C OS. AndM R. 00C B: @ R. 00C RS-P-3As @ R. 00C RS-TK-1: 97 % ENCY BUS (SUPPLY) ' @ DIESEL. DEAD. BACKFEED EMERGENCY' DIESEL GENERATOR (EDG) i H:OP. @ .00C J: OP h. 00C l RESERVE STATION SERVICE B @ / DEAD C M OEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT . A B C REMARKS Total beration of es callons. HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SRRAY RSS - RESERVE STATION SERVICE (A = Ave 11able. R = Running. 00C : Out of Commtssion) 9mef uCDf*v Nahe haAOC /11 % D.Cf [E , joQ j ICRTH Ale 4A POWER STAT]QN 04-01-85 , ,, UNIT 1

~~REACTOR POWER 81.3 %~~

~~' IMARY SYSTEM~~

REACTOR COOLANT SYSTEM (T = Tempereture)- HOTTEST TH see , F HOTTEST TC u, ,* F LOOP'I AT 48.4 F LOOP *2 AT 4g.4 F LOOP "3.iT 48.4 'F i l PRESSURE 2231 PSIG PRESSURIZER LEVEL o %

l PRT LEVEL 68 % REACTOR COOLANT PUMP l As A. N 00C 3 A. @ 00C C: A. M 00C

~~CORE PARAMETERS~~

. CORE EXIT.. THERMOCOUPLE 611.5 *F ..MAROIN.,.TO.. SATURATION Ch A - 43 *F Ch 8 - 43 'F L.. . SOURCE. RANGE _. COUNTS N 31 - one N 32 - ,,, ~4 -4 ... . . . . INTERMEDIATE.. RANGE AM'S N 35 - 4 x 10 N 36 - tsx 10 ,,, RVLIS ime % j L _ , _ , ,, , , _, l CONTAINMENT l 97 oF PRESS. 9.9 PSTA SUMP LEVEL 40 %

~~j. i EMP. .~~

HYDROGEN % l L . . CONT. .!SQLATION PHASE I. II III: ' SECONDARY SYSTEM l l STEAM OENERATOR (LEVEL) i A 44 %B 4'4 % C 44 % AUX. FEEDWATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL o9 %

.3A A. R. @ 3B

$ R. 00C FV-P-2 $ R. 00C ENGINEERED SAF GUARDS - RWST 99 % SIFLOW e (GPM)

HHSI As A. 00C B:($ R. 00C Ca (@ R. 00C OSRS A: /1D R. 00C B:(A) R. 00C .LHSI. A (a/ R. 00C B 40 R. 00C ISRS A [U R. 00C B: O R. 00C . 0S A:S R. 00C B: (Q R. 00C RS-P-3As $O R. 00C, ' ' ' RS-P-38: ' Ti) R. 00C

~~RS-TK-1: 97 /.~~

~~.. ELECTRICAL DISTRIBUTION~~

~~ENCY BUS (SUPPLY)~~

DIESEL. DEAD. BACKFEED (J: RSS) DIESEL. DEAD. BACKFEED E ENCY O!ESEL GENERATOR (EDG) H: OP @ 0OC J: OPh. 00C RESERVE STATION SERVICE As @ EAD B @ EAD' CN/ DEAD (/ HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS ~-o h~, e on w,~, Bank "D" Rods at 189 Steos. O LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eble. R : Rurnung;. 00C = Out of Commission) ,nerw.r., nc.u u em 9. a. n = NAEE Section 10 PLANT STATUS Page 13 of 172 - ICRTH Afe4A POWEA STATION 04-01-85 . . . . . . . _ _ UNIT 1 740 4 g NMR CMION 1 REACTOR POWER 77.1 % C IMARY SYSTEM 4 O REACTOR COOLANT. SYSTEM (T = Temperature)- HOTTEST TH son *F HOTTEST TC ece.a* F LOOP *I AT as.s F LOOP '2 AT y n F LOOP "3 AT 46.6 CF-PRESSURE 2:3s PSIG PRESSURIZER LEVEL eo %- PRT LEVEL sa % 1 REACTOR COOLANT PUMP A A. (D 00C 3, A. (T) 00C C: A. @ 00C CORE' PARAMETERS CORE EXI.T JHERMCCOUPLE sos - *F . . . . . ...MARGIM.IQ. SATURATION Ch A - 47 *F Ch 8 - c 'F ... .. SQURCE. RANGE COUNTS N 31 - eff N 32 - -<< -4 N'36 - 2.2 -4 . _._ INTERMEDIATE RANGE. AMPS N 35 - 4 x 10 x ic , CONT INMENT TEMe.- 97 .F PRESS. 9.9 PSIA SUMP LEVEL 40 % CONT. ISOLATION PHASE I. !!. III: HYOROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 44 % B 44 % 44 % A ,C AUX. FEE 0 WATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL oo % 3As A. R. M 3B: SD R. 00C FV-P-2 @ R, 00C ENGINEEREO SAFEGUAROS - RWST 9a % SI FLOW n (GPM) HHS! As A. $ 00C. B .$ R. 00C C /9 R. 00C OSRS As dD R. 00C g,/10 R. 00C ..LHSI. As @ R. 00C .B: ,(,,O R. 00C ISRS As @ R. 00C B: TD R. 00C OS .As(A)R. 00C B: 7Q R. 00C RS-P-3A: 4Q R. 00C, ' RS-P-3B: /O R. 000 l RS-TK-1: oi % ELECTRICAL DISTRIBUTION l EMERGENCY BUS (SUPPLY) <$ RSQ DIESEL. DEAD. BACKFEED @ DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP @ 00C J: OP@ 00C RESERVE STATION SERVICE A:O CEAD. B@/ DEAD ' CtODEAC HIGH RANGE EFFLUENT RA0 MONITORS . VENT VENT _,, PROCESS VENT MAIN STEAM A _B C 9EMARKS n,+ "na w ,- so, w LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEA0 S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available. R = Running. 00C : Out of Commission) enceuene.v ne.u =oe m _ _ 9. a. a . , ~ PLANT STATUS QE e ct}oQ0 o 04-01-85 l@tTH ANNA PowtR STAT 10N UNI 1 ~ 711.5 gsw MMEWER CPUCN 1 , RY SYSTEM ' REACTOR COOLANT. SYSTEM (T = Temperature)- HOTTEST TH 599.*F HOTTEST TC sss 'F 44.6 *F Loop e2 AT 44.s F Loop og AT 44 3 og LOOP *I AT PRESSURE 222s PSIG PRESSURIZER LEVEL ss % PRT LEVEL sa % REACTOR COOLANT UMP A: A. R. 00C g: A. @ 00C C: A. @ 00C CORE PARAMETERS . . CORE;.EXI.T.. THERMOCOUPLE 604.5 'F .._ . MARGIN .Ta. SATURATION Ch A - 49 *F Ch 9 - 49 *F , . _ _ ..__ SOURCE.. RANGE. COUNTS N 31 - off N 32 - off -4 ~4 . ___.._ INTERMEDIATE... RANGE AMPS N 35 - 4 x 10 N 36 - 2.2 x 10 RVLIS 100 % _ _ _ _ ~}, CONTAINMENT 97 oF PRESS. o., PSIA SUMP LEVEL 40 % TEMP.. CONT. ISOLATION PHASE I. II. III: HYOROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 44 %B 44 % C da % A. o (GPM) CN-TX-1/2 LEVEL 99 % . AUX. FEED FLOW

~~0. AUX. 3At FEEDWATER A. R. 6 .. @~~

38: R. 00C FV-P-2 O R. 00C-99 % SIFLOW n (GPM) ENGINEERED SAFEGUARDS - RWST ' HHSI A A. (@ 00C.. . B: $ R. 00C C: 62 R. 00C OSRS As /1VR 00C gg /O R. 00C . LHSI As (M R. 00C .B: CA/ R. 00C ISRS A: /O R. 00C Bi iiQ R. 00C OS. As fC R. 00C B: /0 R. 00C RS-P-3A: dQ R. 00C -" RS-P-38: (@ R. 00C RS-TK-1: 97 % ELECTRICAL OISTRIBUTION ' EMERGENCY BUS (SUFFLY) <Q RSp OIESEL. OEAO _ BACKFEED BACKFEE0 Q'RSf OIESEL. DEAD EMERGENCY OIESEL GENERATOR (EDG) H:OP, h .00C J: OP.@ 00C RESERVE STATION SERVICE . M OEAD B S / DEAD EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C ~ MARKS Total boration of us calions. Bank "D" Rods at 188 Stees. LEGENO: HHSI - HIGH HEAD S.I. OSRS - GUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE 1 (A - : Ave 11able. R = Running. 00C = Out of Commission) - _ _ - m_ m __ m _ PLANT STATUS. NAEE Section 10 , Page 15 of 172 . PGRTH APMA POWER STATICN 04-01-85 _f UN!h .13f4 1 .g s 664 3 MWEWER OFTICN l' , RY SYSTEM REACTOR COOLANT SYSTEM (T

Temperature) - HOTTEST TH s97.*F HOTTEST TC sss.3*F LOOP"1 AT 42.1 F LOOP *2 AT 43.1 F LOOP 83 AT 42.1 CF PRESSURE nn4, PSIG PRESSURIZER LEVEL , ss %

L PRT LEVEL se % REACTOR COOL /NT PUMP As A. R. 00C g, A. R. _0CC C: A. R. 00C CORE PARAMETERS ---- . CORE EXIT.. THERMOCOUPLE 602.5 *F

~~_. ..... . MAROIN TO. SATURATION Ch A -~~

52 *F Ch 8 - 52 'F _ SOURCE _ RANGE . COUNTS N 31 - off N 3l? - err N,.36 - 2 x 10 ~4 -4 [ _ . ._INTERME0! ATE..8ANGE AMPS N 35 - 4 x 10 RVLIS too % i CONTAINMENT . '~ 9, oF PRESS. 99 PSIA SUMP LEVEL 40 % TEMP. . CONT. ISOLATION PHASE I II. III: HYOROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) . A 43 % B 44 % C 44 % AUX. FEE 0 WATER . AUX. FEED FLOW n (GPM) CN-TK 1/2 LEVEL 99 %' 3As A. R. 00C 3B: A. R. 00C FW-P-2 A. R, 00C ENGINEERED SAFEGUARDS - RWST 99 % SI FLOW o (GPM) .HHSI A A. R. 00C B: A. R. 00C C: A. R. 00C OSRS A: A. R. 00C B: A. R. 00C -LHSI As A. R. 00C B A, R. 00C ISRS A A. R. 00C B: A. R. 00C -.. 05. As A. R. 00C B: A. R. 00C RS-P-3A: A. R. 00C RS-P-3B A. R. 00C RS-TK-!: 97 % ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) H: RSS, DIESEL. DEAD. BACKFEE0 J:RSS. DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (E00) H: OP. AVAIL. 00C J: OP. AVAIL. 00C RESERVE STATION SERVICE , As HOT /OEAO. .. B: HOT / DEAD C: , HOT / DEAD HIGH RANGE EFFLUENT RAD MONITORS E VENT VENT ,, PROCESS VENT MAIN STEAM A B C MARKS Total beration of 13s eations. Bank "D" Rods at 185 Steps. LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Avellable. R = Running. 00C = Out of Commission) peANT STATUS NAEE Section 10 Page 16 of 172

~~PORTH Ape 4A POWER STAT]ON 04-01-85 gf = 2 3~~

~ 618. 5 g MANEUVER CPTION 1 REACTOR POWER 64.6 % IMARY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 593. ?F HOTTEST TCssa.i'F LOOP *1 AT 39.4 F LOOP *2 AT 39.4 F Loop m3 A7 39.4 og PRESSURE 2234 PSIG PRESSURIZER LEVEL s2 % PRT LEVEL 68 % REACTOR COOLANT PUMP 4, A. $ 00C g, A. $ 00C C: A. N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 597 S *F . .__ . _ MARGIN TO SATURATION Ch A - 55 *F Ch 8 - 55 'F . . . . SOURCE. RANGE COUNTS N 31 - off N 32 - off ~4 -4 _.. _ ._ INTERMEDIATE . RANGE AMPS N 35 - 3.8 x 10 N 36 - 2 x 10 RVLIS 100 % , CONTAINMENT TEMP._ 9, oF PRESS. 9.9 PSIA SUMP LEVEL 40 % . __ ... CONT. ISOLATION PHASE I. II. III: HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 44 % B 44 % C 44 % AUX. FEE 0 WATER AUX. FEED FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % O l 3As A. R. @ 39: Q - R. 00C FW-P-2 @ R. 00C l ENGINEERED SAFEGUARDS - RWST ' go % SIFLOW n (GPM) HHSI As A.@ 00C - 8: @ R. 00C C: & R. 00C OSRS A: <1Q R, 00C B:/C R. 00C ~ LHSI As/3) R. 00C B dD R. 00C ISRS A: % R. 00C B: TO R.' '00C OS A:/D R. 00C B: /4 R. 00C RS-P-3A: 2E) R. 00C " ~ ~ ~ RS-P-38: CV R. 00C RS-TK-1: 97 % . ELECTRICAL DISTRIBUTION El

~~ENCY BUS '(SUPPLY)~~

R DIESEL. OEAD. BACKFEED OEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) @ DIESEL. H:OP. h 00C J: OP.h. 00C RESERVE STATION SERVICE . A(EdDOEAD . B M OEAD C M DEAD ' HIGH RANGE EFFLUENT RAD MONITORS VENT' VENT PROCESS VENT MAIN STEAM A B, C REMARKS sank "o" Reds at iss stees. Total beration of 13s caliens. , on. aAa A. . v 4 1 i s .... o-iio. na -1 3-o - ., a . . y . oo, uona. l l LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Ave 21eble. R = Runn2ng. 00C : Out of Commission) ' AANT $TATUS NAEE Saction 10 . 2-1/4 NORTH ANNA POWER STAT]QN [*8',lhf172 1, 9 1

~~e. xw muvra orTIcu 1 g ,~~

RY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 592.9F HOTTEST TC 556.2* F LOOP'1 AT 36.1 F toop .2 AT 3s.1 F LOOP #3 AT 36.1 CF PRESSURE 2226 PSIG PRESSURIZER LEVEL =, % PRT LEVEL sa % REACTOR COOLANT PUMP A: A. (T) 00C g, A. @ 00C C: A. @ 00C CORE PARAMETERS . . CORE EXIT THERMOCOUPLE 596 *F .. . . MARGIN TO SATURATION Ch A - 56 *F Ch 8 - 56 'F _ __..__. SOURCE RANGE COUNTS N 31 - off N 32 - off ~4 . .__ _ INTERMEDIATE RANGE AMPS N 35 - 3.2 x 10 N 36 - 1.9 x lo'4 ,, RVLIS 100 % F PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP.- 9., CONT. ISOLATION PHASE I. II. III: HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) . A 44 % B 44 % C da % AUX. FEEDWATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL o9 % 3As A. R. b 38: /1C R. 00C FW-P-2 f5D R, 00C ENGINEERED SAFEGUARDS - RWST co % SIFLOW n (GPM) HHSI A A. O OOC B ($) R. 00C C: @ R. 00C OSRS As /% R. 00C 8: /6) R. - 00C LHSII A /OR. 30C B (E R. 00C ISRS A ~5C R, 00C Ba h R. 00C OS A:/O R. OCC B : (_ d R. 0 0 C RS-P-3A J) R. 00C ~ RS-P-38: 70 R. 00C RS-TK-1: 97 % ELECTRICAL DISTRIBUTION iMER0ENCY BUS (SUPPLY) 6j?: DIESEL. DEAO. BACKFEED h DIESEL. DEAO BACKFEE0 EMERGE DIESEL GENERATOR (EDG) H: O'P. VA .00C J:O h 00C RESERVE STATION SERVICE A(T03/0EA0 . B@/DEAO ' C:hCEAR HIGH RANGE EFFLUENT RA0 MONITORS VENT VENT __. PROCESS VENT MAIN STEAM A B C REMARKS went so m i n., - , i c n .. . , u _ Bank "o" peas at 191 sees. LEGEND: HHSI - HIGH HEA0 S.I. OSRS - OUTSIDE RECIRC. SPRAY ! LHSI - LOW HEA0 S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Ave 11eble. R = Running. 00C = Out of Commission) .~.-. .,,. ~.u u..,,, e. .. o r, ~ l PLANT STATUS NAEE Section 10 Page 18 of 172 * = 2-1/2 l@RTH Am POWER STAT]QN 04-01-85 UNIT 1 s21 MW MA!EUVER CFTICt! l , IMARY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH ses.?F HOTTEST TC 551.9 *F 34 F Loop 2 AT 34 F LOOP 3 AT 34 CF LOOP'I AT l J PRESSURE 2236 PSIG PRESSURIZER LEVEL g % PRT LEVEL 68 % REACTOR COOLANT UMP A A. R 00C 3 A. @ 00C C: A. @ 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 599.s *F ~ __ MARGIN TO SATURATION Ch a . 63 *F Ch 8 - 63 *p , ~ ... . ... . SOURCE RANGE COUNTS N 31 - off N 32 - off ~ . . . . . INTERMEDIATE RANGE. AMPS N 35 - 3.1 x lo N 36 - 1.9 x lo" " RVLIS loo % ' ' ~ CONTAINMENT TEMP. 9, oF PRESS. 9.9 PSIA SUMP LEVEL 40 % CONT. ISOLATION PHASE I. II. IIh HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 44 % B 44 % C 44 % l AUX. FEEDWATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % 3As A. R. O 38: (AD R. 00C FW-P-2 /R) R. 00C ENGINEERED SAFEGUARDS - RWST 99 % SIFLOW o (GPM) ! HHS! A A. @ 00C B ($) R. 00C C: (@ R.00C OSRS A (5) R. 00C B: #) R. 00C~ -LHSI A 70 R. 00C B: @ R. 00C ISRS As 'rE) R. 00C B: i@ R. 00C .. OS AirO R. 00C B: S0) R. 00C RS-P-3A ' (@ R. 00C . ' RS-P-38: @ R. 00C ' RS-TK-1: 97 % ELECTRICAL DISTRIBUTION . E R NCY BUS (SUPPLY) RS DIESEL, OEAD. BACKFEED h DIESEL. DEAO, BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP. @ 00C J: OP,@ 00C l RESERV STATION SERVICE , A / DEAD B:M OEAD C DEAL HIGH RANGE EFFLUENT RAD MONITCRS VENT VENT ,_ PROCESS VENT MAIN STEAM A B C REMARKS nas "na neas it tai seers nute m ana vain e.w. pn-e _ LEGEND: HHSI - HIGH HEAD S.I. OSRS - GUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY 05 - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 11eble. R = Running. 00C = Out of Commission) ,nwm m m mm AANT STATW NAEE Section 10 Page 19 of 172 *- 2-3/4 PORTH AM4A POWER STATION 04 01-85 UNIT 1 493. 3 w MANEUVER OFTICt! l (jS . ~ C*l! MARY SYSTEM , b REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 584 JF HOTTEST TC5s3. 3

F 31.2 *F Loop 2 AT 31.2 F LOOP "3 AT n.2 *F LOOP'1 AT PRESSURE ms PSIG PRESSURIZER LEVEL 48 %

PRT LEVEL 68 % REACTOR COOLANT UMP A A. R. 00C B: A. 00C C: A. N 00C CORE PARAMETERS CORE EXIT THERMOCOUPLE 586 op .. MARGIN TO SATURATION Ch A . 65 oF Ch B - 65 *F .. SOURCE RANGE COUNTS N 31 - off N 32 - off -4 . . . INTERMEDIATE RANGE. AMPS N 35 2.9 x 10 N 36 - 1 6 x 10 RVLIS m, % CONTAINMENT 97 eF PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP. CONT. ISOLATION PHASE I. !!. III: HYOR00EN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 44 %B 44 % C 44 % A AUX. FEE 0 WATER AUX. FEED FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % 3As A. R. (600D 38: (4") R. 00C FV-P-2 /T) R, 00C 99 % o (GPM) ENGINEERED SAFEGUARDS - RWST HHSI As A.@ 00C 8: /@ R. 00C C @ R. 00C SIOSRS FLOW As / _ O R. 00C B:/O R. 00C~ LHSI A (42 R. 00C 8: @ R. 00C ISRS As /C R, OOC Ba' @ R. 00C

~~05. A (Q R. 00C B: @ R. 00C RS-P-3A: @ R. 00C ~~ '~~

RS-P-38: /1D R. 00C RS-TK-1: 97 % .. ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) @ DIESEL. DEAD. BACKFEED @ , DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EOG) H: OP.@. 00C J: OP.@. 00C RESERVE " STATION SERVICE A 60T) DEAD. B:3I6Y) DEAD" C(1@T70EA0 HIGH RANGE EFFLUENT RAD MONITORS k VENT VENT , , , PROCESS VENT MAIN STEAM A B C -REMARKS Bank "o" ae do at 179 stees __ O Total boration of 180 crallons. V ~ LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A Avelle61e. R : Running. 00C = Out of Commsssion) "' ~c** ? " - "***'" . '-**** AANT STATUS NAEE Section 10 Page 20 of 172 7 3 NORTH ADMA POWER STATION 04-01-85 UNIT 1 ng s . mat:rwta crgert i , D IMARY SYSTEM d REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH se2.e*F HOTTEST TC sss.t* F LOOP'1 AT 26.8 *F LOOP '2 AT 25 F LOOP "3 AT 26.e of PRESSURE 2226 PSIG PRESSURIZER LEVEL ac % PRT LEVEL se % REACTOR COOLANT PUMP A A. @ 00C 3 A. N 00C C: A. I 00C , CORE PARAMETERS . CORE. EXIT.. THERMOCOUPLE ses *F .. . MARGIN TO . SATURATION Ch A - 68 *F Ch B - , 68 F . ... . . SOURCE. . RANGE.. COUNTS N 31 - off N 32 - off ~4 _ . ...._.. INTERMEDIATE . RANGE _ AMPS N 35 - 2. 2 x 10 N 36 - 1.2 x lo'4 , R IS 100 % ,, , ,,,_ , ,,,,,,. 97 F PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP. , , , . .. CONT. ISOLATION PHASE I. !!. III: HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 44 % B 44 % C 44 % ( AUX. FEEDWATER AUX. FEED FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % 3As A. R, M 38: O R. 00C FW-P-2 $ R. 00C ENGINEERED. SAFEGUARDS - RWST 99 % SIFLOW o (GPM) HHSI - As A.O OOC B@ R. 00C C: (O R. 00C OSRS A (AJ R. 00C BirO P. 00C

1. .LHSI.. A /iG R. 00C B: 4D R. 00C ISRS As @ R. 00C B: WR. 00C l - -.0S ~ AndD R. 00C B: 70 R. 00C RS-P-3A: rQ R. 00C ~ ~ ~ '

l RS-P-3B: 4D R. 00C . . . . . . RS-TK-1: 97 % ELECTRICAL DISTRIBUTION , EME TNCY BUS (SUPPLY) ' RS DIESEL. DEAD. BACKFEED @ DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP< @ 00C J'OP. @ ,00C RESERVE STATION SERVICE ' AdIQ7/ DEAD. Bdi@/ DEA 0 CdIO'T)/ DEAD y HIGH RANGE EFFLUENT RAD MONITORS / .. VENT VENT . PROCESS VENT MAIN STEAM A B C l , REMARKS Bank "D" Rods at 174 Stees. l *otal beration of 20s ma!!cns - ,, Remove reheaters fr0m service. LEGENO: HHSI - HIGH HEA0 S.I. OSRS - OUTSIDE RECIRC. SPRAY l LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY l OS - QUENCH . SPRAY RSS - RESERVE STATION SERVICE (A = Avetleble. R = Running. 00C : Out of Commissten) Tmet h acOf*.y nt*.M M664 #11 *). A. A 8C _/ PLANT STATUS NAEE Section 10 NORTH AMA POWER STATION $$185 UNIT 1 ~ m W .WEWER CPTIoN 1 , RY SYSTEM . REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH so.?F HOTTEST TC544.e 'F - LOOP *1. AT 23 *F Loop .2 AT 23 *F Loop m3 AT 23 CF- l J PRESSURE , 2227 PSIG PRESSURIZER LEVEL 30 % PRT LEVEL 68 % REACTOR COOLANT PUMP A A. /T) 00C 3 A. h 00C C:. A. N 00C I CORE PARAMETERS . CORE EXIT. THERMOCOUPLE 571 *F ~ 82 *F 82 op l ... .. MARGIN. IQ _SATURATJON Ch A - Ch 9 ..- .. .. SOURCE. BANGE...COUN. T S N 31 - off N 32 - off . ___ INTERMEDIATE _ RANGE. AMPS N 35 2 x 10 ' N 36:- ,J3n ~4 ~' RVLIS 100 % a, F PRESS. 9.9 PSIA SUMP LEVEL 40 %- TEMP l _. CONT. ISOLATION PHASE I. II. III: HYDROGEN % . SECONDARY SYSTEM STEAM GENERATOR (LEVEL) _ .A 44 % B 44 % C 44 % 1 AUX. FEEDWATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % 3As. A. R. N 38: /C R. 00C FV-P-2 (3 R, 00C ENGINEERED SAFEGUARDS - RWST 99 % SIFLOW o (GPM) . HHSI As A.OOOC B: (B R. 00C C ($ R. 00C OSRS As g2 R. 00C B: 4) R. 00C, _ LHS! As/O R. 00C B: (@ R. 00C ISRS As M R. 00C B: au R. 00C .. OS A/O R. 00C B: /4 R. 00C RS-P-3A: " /Q R. 00C RS-P-38: & R. 00C . . . RS-TK-1: 97 % ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) @ DIESEL. DEAD. BACKFEED @ DIESEL. DEAO. BACKFEEE EMERGENCY DIESEL GENERATOR (EDG) H:OP. S .00C J: OR@. 00C RESERVE STATION SERVICE AscWl5T) DEAD . . B M EAD' C @ /DE K. HIGH RANGE EFFLUENT RAD MONITORS VENT VENT .. PROCESS VENT MAIN STEAM A B C REMARKS sank "D" Rods at 177 steps. Remove H.P. Heater Drain Pumps from service. { LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.L ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Ave 21eble. R = Running. 00C = Out of Commission) - '"" "'!T_"2 _ " # '" 2f r PLANT STATUS NAEE Section 10 NORTN AMA POWER STAT]QN 0$801NS NIT 1 ;.A 287 Mw MANEUVER OFTICt 1 REACTOR POWER 35.4 % l , RY SYSTEM l : REACTOR COOLANT SYSTEM (T = Tempereture) - HOTTEST TH ss3.f F HOTTEST TC 541.? F LOOP *1 AT 22.2 F LOOP '2 AT 22.2 *F LOOP "3 AT 22.2 CF PRESSURE 2247 PSIG PRESSURIZER LEVEL 2e % ! PRT LEVEL 68 % , L REACTOR COOLANT P MP L A A. 00C B: A. @ 00C C: A. @ 00C L CORE PARAMETERS 568 op CORE. EXIT THERMOCOUPLE

~~l. _~~

l MARGIN TO SATURATION Ch A - es *F Ch 8 - 96 *F ~' L...... SOURCF. RANGE . COUNTS N 31 - off N 32 - off -4 ~4 . . . . . _ . . INTERMEDIATE.. RANGE AMPS N 35 - 2 x 10 N 36 - 1 x 10 , l' RVLIS 100 % .....-.! L L 97 F PRESS. 99 PSIA SUMP LEVEL 40 % ~ TEMP. , CONT. ISOLATION PHASE I. II. III: HYDROGEN % i SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 44 % B 44 % C 44 % AUX. FEEDWATER. AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % ! 3As . A. R. 38: O R. 000 FV-P-2 dO R, 00C ENGINEERED SAFEGUARDS - RWST 99 % SI FLOW o (GPM) HHSI As A.h 00C. Bt(@ R. 00C C: /S) R. 00C OSRS A: MQR. 00C B:/Q R. 00C , LHSI As/S R. 00C B: S R. 00C ISRS A .@ R. 00C 8:(9 R. 00C OS A:/Q R. 00C B (@ R. 00C RS-P-3A s0 R. 00C ~ ~ RS-P-38: (O R. 00C RS-TK-!: 97 % ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) . BACKFEED (@ DIESEL. DEAO. BACKFEED c @ OIESEL. DEAD EMERGENCY. DIESEL GENERATOR (EDG) H: OP8 00C J: OP.@ 00C RESERVE STATION SERVICE And@DOEAD B M DEAO' C;[T/CEAC HIGH RANGE EFFLUENT RAD MONITORS VENT VENT _ PROCESS VENT MAIN STEAM A B C REMARKS Bank "D" Rods at 183 Steos. LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY 05 - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available. R : Running. 00C Out of Commission) ener-c.v nr.u . u.ac q 2 a.as AANT STATW NAEE Section 10 Page 23 of 172 , NORTH Ape 4A P0wtR STATION 04-01-85 . , , UNIT 1 %' - 2 s 4. 4 :4w MArawra emet 1 p , Y SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 567. 0F HOTTEST TC t48.s

~~F LOOP *! AT 19.4 F LOOP *2 AT ia 4~~

*F LOOP m3 AT 19.4 0F PRESSURE 2232 PSIG PRESSURIZER LEVEL 33 % PRT LEVEL 68 % REACTOR COOLANT PUMP A A. (Id 00C g A. @ 00C C: A. @ 00C CORE PARAMETERS ... CORE. EXII_ THERMOCOUPLE 57o.5 op . _ . . . MARGIN .TO SATURATION Ch A - 82 'F Ch B - 82 'F off N 32 - off ..__. .__. SOURCE . RANGE. COUNTS N 31 - -4 -5 ... . ___INIERMEDIAIE. RANGE AMPS N 35 - 1.9 x 10 N 36 - s x 10 RVLIS too % , _. [, i CONTAINMENT. 9, oF PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP. ... CONT. ISOLATION PHASE I II. III: HYOROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 45 % B u % C 47 % AUX. FEEDWATER AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % 3As A.. R. M 38: rd)" R. 00C FW-P-2 @ R. 00C ENGINEERED SAFEGUARDS - RWST 99 % SIFLOW o (GPM) : HMSI As A.@ 00C Ba @ R. 00C C: @ R.00C OSRS As d7 R. 00C g:40 R. 00C ~ LHSI As dD R. 00C B: /2D R. 00C ISRS As /O R. 00C B: MQ R. 00'C . QS As ,C R. 00C ~ B: /0 R. 00C RS-P-3A: (O R. 00C ' RS-P-3B (1Q R. 00C . RS-TK-1: 97 % ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) DEAD. BACKFEED @ DIESEL. DEAD. BACKFEED [ @ DIESEL. EMERGENCY DIESEL GENERATOR (EDG) H:OP h .00C J:OPpWAID00C v RESERVE STATION SERVICE ~ A M EAD B M / DEAD C M OEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT , , , PROCESS VENT MAIN STEAM A B C ARKS =ank "na e ~an at 4a, e ons. .p' Place F.W. Bveasses in Auteratic. LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eblo. R = Running. 00C : Out of Commission) ,m ~~ruw m Pt. ANT STATtJS NAEE Section 10 NORTH AMA POWER STATION o$ $.1N5 NIT 1 m 216.8 w - WJiEUVER OPTICt! l , D IMARY SYSTEM d REACTOR COOLANT. SYSTEM (T = Temperature) - HOTTEST TH 566.iPF HOTTEST TC sso.'4* F LOOP'1 AT 16.5 F Loop e2 AT is.s F LOOP "3 AT 16.s *F PRESSURE 2237 PSIG PRESSURIZER LEVEL 23 % PRT LEVEL sa % REACTOR COOLANT PUMP As A. @ 00C ga A. @ 00C C: A. @ 00C CORE PARAMETERS .. CORE EXIT . THERMOCOUPLE 569 *F .. .. MARGIN TO SATURATION Ch A - 94 *F Ch 8 - 94 *F . _ . . SOURCE.. RANGE COUNTS N 31 - off N 32 - off ~ . .... _._. INTEBMEDIATE. RANGE . AMPS N 35 1 5 x 10'" N 36 - 8 x 10 ~ l RVLIS 100 % '~ ~ ~ CONTAINMENT 97 oF PRESS. 9.9 PSIA SUMP LEVEL 40 % TEMP.- l < , CONT. ISOLATION PHASE I. II. III: HYDROGEN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 44 %B 44 % C 44 % , A 1 AUX. FEEDWATER ' AUX. FEE 0 FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % 3As A. R: O 38: @ R. 00C FW-P-2 @ R. 00C 99 % SI FLOW o (GPM) ENGINEERED SAJF GUARDS - RWST l HHSI As A. diV 00C B: (@ R. 00C C: @ R. 00C OSRS As /4) R. 00C B:$ R. 00C . 'LHSI2 A /D R. 00C B: /C R. 00C ISRS A: (O R. 00C 8: @ R. 00C OS A /C R. 00C B:/S R. 00C ' RS-P-3A: /T) R. 00C ' RS-P-38: @ R. 00C ~ . . . . . RS-TK-1: ~ 97 % ELECTRICAL DISTRIBUTION EMER ENCY BUS (SUPPLY) RS~ DIESEL. DEAO. BACKFEED h. DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP h .00C J: OP.@. 00C RESERVE STATION SERVICE Aa45DOEA0 B:M /DEAO' C:6dDOEAQ HIGH RANGE EFFLUENT RAD MONITORS h VENT VENT PROCESS VENT MAIN STEAM A B C REMARKS sank "o" Rods at 183 steps. _ Place Main F.W. Rec. Valves in Manusl. , , , LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - GUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eble. R = Running. 00C = Out of Commission) Terrucany MN. , N6pC /11 7 R. AM . , PLANT STATUS NAEE Ssction 10 fGRTH AM4A POWER $7ATICN o$"$1N5UNIT 1 3 n, 3 MANEUVER CPTIOtt 1 p N IMARY SYSTEM D REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 56s.0F HOTTEST TC ss2.s* F - LOOP *1 AT 13.2 *F Loop 2 AT 13.2 *F LOOP "3 AT 13.2 0F PRESSURE 2198 PSIG PRESSURIZER LEVEL 36 % PRT LEVEL 68 % REACTOR COOLANT UMP As A. R 00C g, A. @ 00C C: A. N 00C CORE PARAMETERS . CORE EXIT ' THERMOCOUPLE 567 *p - _ MARGIN TO. SATURATION Ch A - 88 *F Ch 8 - 88 'F . . . . .. SOURCE RANGE, COUNTS N 31 - off N 32 - off i -5 --. _... . INTERMEDIATE RANGE AMPS N 35 - 1 x 10" N 36-- 6 x 10 ~ RVLIS too %- ~~ ~ ~ ' CONTAINMENT , TEMP. 97 oF PRESS. 9.9 PSIA 40 % SUMP LEVEL. _ E CONT. ISOLATION PHASE I. II. III: HYOROGEN % SECONDARY SYSTEM l STEAM- GENERATOR (LEVEL) A 42 %B 40 % C 42 % AUX. FEED FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % AUX. FEEDWATER 3As A. R. M 38: fD R. 00C FW-P-2 $ R. 00C 99 0 (GPM) ENGINEERED SAFEGUARDS - RWST % SIFLOW , HHSI As A.@ 00C B: @ R. 00C C: @ R. 00C OSRS As @ R. 00Q., . 3: 40) R. 00C ' . LHSI As (2D R. 00C B @ R. 00C ISRS At 40 R. 00C B: @ R.00C OS A:642 R. 00C B: @ R. 00C RS-P-3A: /Q R. 00C ~ RS-P-38: O R. 00C RS-TK-1: 97 % ELECTRICAL DISTRIBUTION E NCY BUS (SUPPLY) ; DIESEL DEAO. BACKFEED BACKFEED

h. DIESEL. DEAO E RGENCY O!ESEL GENERATOR (EDG) l H:OP p .00C J: OP @. 00C l ' RESERVE STATION SERVICE .

.Asdf0DOEAD BM/ DEAD C / DEAD HIGH RANGE' EFFLUENT RAD MONITORS I VENT VENT ,, PROCESS VENT MAIN STEAM A B C l MARKS Bank "D" Rods at 183 Steps l LEGENO: HHS! - HICH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY l LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY I- OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE [ (A = Ave 21oble. R = Running. 00C = Out of Commission) J REE Scdion 10 PLANT STATUS Page 26 of 172 = -1/2 M3RTH MedA POWER STAT]ON 04-01-85 17 9. 6:4w MANEUVER oPMoN 1 REACTOR POWER is n 1 ;IMARY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 559.?F HOTTEST TC 549.9F L ' LOOP'1 AT 10 F LOOP *2 AT lo ' F LOOP "3 AT' 10 *F PRESSURE ,__ 224o PSIG PRESSURIZER LEVEL 31 % PRT LEVEL 68 % ~ REACTORCOOLAN@TPUMP As A. 00C 3 A. [C 00C C: A. @ 00C l CORE PARAMETERS . . .. CORE EXIT THERMOCOUPLE ss2 'F . __.... MAROIN TO.. SATURATION Ch A - 91 *F gh B - 91 *F ,, L _ ......._ SOURCE RANGE. COUNTS N 31 - off N 32 - off - -5 -5 l ._.._._____.INIERMEDIATE RANGE. AMPS N 35 - 7 x 10 N 36'- s x 10 RYLIS 100 % 97 F PRESS. o., PSIA SUMP LEVEL 40 % l TEMP.. , , , ! __. CONT. ISOLATION PHASE I. II. III: HYOR00EN % -SECONDARY SYSTEM STEAM OENERATOR (LEVEL) A 39 %B 40 % C n % AUX. FEE 0 WATER AUX. FEED FLOW 0 (OPM) CN-TK-1/2 LEVEL 99 % 3A: A. R. M 38: <1!ID R. 00C FV-P-2 (A) R. 00C ENGINEERED SAFEOUARDS - RWST 99 % SI FLOW 0 (OPM)~ HMSI As A.@ 00C Ba $ R. 00C C: <O R. 00C OSRS As /C R. 00C B:.T) R. 00C ' LHS! A /T R. 00C B:/% R. 00C ISRS A:' 4 R. 00C B:@ R. 00C . QS.. As(10 R. 00C B: @ R. 00C RS-P-3A~ @ R. 00C . RS-P-38: /1D R. 00C s RS-TK-1: 97 % ' ELECTRICAL DISTRIBUTION E NCY BUS (SUPPLY) ' RS DIESEL. DEAD. BACKFEED (f:RSS) DIESEL. DEAD. BACKFEED EMERGENCY DIESEL OENERATOR (E00) H:OP. @ .00C J:OP @ .00C RESERVE STATION SERVICE - As MSDOEAD B:M /CEAD C:M/ DEAD. HIGH RANCE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C "EMARKS Bank "D" Reds at 183 steps. (d . LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21ebloo R : Runnan@b_00C = Osa ef Cemnogased PLANT STATUS NAEE Sect 1on 10 l Page 27 of 172 7 4 3/4 1 NORTH Ape 4A POWER STATION 04-01-85 _ UNIT 1 m' 3n, a m e wra ort:oM 1 , t C IMARY SYSTEM , V REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 557.SF* HOTTEST TC 549.2

F l B.4 F Loop e2 AT. 8.4 F LOOP "3 AT 8.4 oF l LOOP'1 AT PRESSURE 2234 PSIG PRESSURIZER LEVEL 2s % l PRT LEVEL 68 %

REACTOR COOLANT PUMP As A. (fQ 00C- B: A. @ 00C C: A. @ 00C CORE PARAMETERS - - . . CORF.. EXIT THERM 0 COUPLE 559 'F _. .. ._... MARGIN. TO SATURATION Ch A - 95 *F Ch 9 - 95 *F _, off N 32 - off ...... .._ SOURCE RANGE COUNTS N 31 - N 36 - -5 . INTERMEDIATE RANGE AMPS N 35 - 6 x 10' 2.s x 10 __ RVLIS 100 % 97 F 9.9 PSIA SUMP LEVEL 40 % TEMP PRESS. . CONT. ISOLATION PHASE I. !!. III: HYOROGEN % i SECONDARY SYSTEM STEAM GENERATCR (LEVEL) A- 37 % B 38 % C 39 % ,l AUX. FEE 0 FLOW 0 (GPM) CN-TX-1/2 LEVEL 99 % ; O' AUX. FEE 0 WATER V 3As . A.- 'R. 6 38: (dD R. 00C FW-P-2 (T) . R, 00C ENGINEEREO SAFEGUARDS - RWST 99 % SI FLOW o (GPM)- HHSI A: A. @ 00C Bs. @ R. 00C C: @ R. 00C- OSRS A: 40 R. 00C B (@ R. 00C ; LHSIl A /1D R. 00C B: dD R. 00C ISRS A: ,1 C R .' 0 0 C B: @ R',' 00C l B: JD R. 00C RS-P-3A: @ R. 00C ~ OS A:(T R. 00C ' ~ ~ RS-P-38: (1D R. 00C RS-TK-1: 97 % i ELECTRICAL DISTRIBUTION . .E NCY' BUS (SUPPLY) RS DIESEL. DEAD. BACKFEED h DIESEL. DEAO. BACKFEED E RGENCY DIESEL GENERATOR (E00) . H:OP p OOC J: OPh. 00C . RESERVE STATION SERVICE ' ' A /@D'OEAD. . BidIdd'OEAD C:didT) DEA 0 'HIGH RANGE EFFLUENT RA0 MONITORS VENT VENT ,_, PROCESS VENT MAIN STEAM A B C REMARKS Bank "o" Rods at 193 steps. j LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eble. R = Running. 00C : Out of Commission) NAEE Section 10 L PLANT STATUS Page 28 of 172 04-01-85 b NORTH Af444 POWER STATION , , _ , UNIT 1 64 MW MANEUVER CPTICN-l~ d .. REACTOR POWER e.e % , G IMARY SYSTEM , i REACTOR C00LANL. SYSTEM (T = Temperature)- HOTTEST TH 549 'F HOTTEST TC 554 'F LOOP *1 AT s F LOOP *2 AT s F toop .3 AT s CF , PRESSURE 2235 PSIG PRESSURIZER LEVEL 25 % PRT LEVEL sa % L REACTOR COOLANT PUMP As A. (TQ 00C B: A. @ 00_C C:- A. h '00C CORE PARAMETERS ! .. CORE EXIT THERMOCOUPLE 555 *F ".. . .MARDIN TO. SATURATION Ch A . 98 *F Ch 8 - 98 'F , . .. . SOURCE RANGE COUNTS N 31 - off N 32 - off ~ - ._.. .. INTERMEDIATE RANGE. AMPS N 35 3 x 10" N 36 - 2 x 10" '-~ RVLIS 100 % CONTAINMENT. TEMP. - 9, oF PRESS. 9.9 PSIA SUMP LEVEL 40 % ! HYOROGEN % ! . CONT. ISOLATION PHASE I. II. III,a SECONDARY SYSTEM l STEAM GENERATOR (LEVEL) l .A

~~34 %B 35 % C- 35 %~~

! 0 AUX. FEED FLOW (GPM) CN-TK-1/2 LEVEL 99 % O AUX. FEE 0 WATER l V 3As A. R. 6 38: @ R. 00C FW-P-2 M R. 00C t 99 % SIFLOW o (GPM) ENGINEERED SAFEGUARDS - RWST _ HHSI A A.<@ 00C B (9 R. 00C C: ($ R. 00C OSRS A (O R. 00C B: /O R. 00C LHSI A 7O R. 00C Ba @ R. 00C ISRS A (O R, 000 B:4 ' R.' 0 0 C .. 05 A:MO R. 00C B: (O R. 00C RS-P-3As (D R. 00C RS-P-30: /Q R. 00C RS-TK-1: 9, % . ELECTRICAL DISTRIBUTION ~ EMERGENCY BUS (SUPPLY) H@ DIESEL. DEAO. BACKFEED Jh DIESEL. DEAO, ~ BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP. @. 00C J: OP.@, 00C RESERVE STATION SERVICE A:6idDOEAD. B:dId@/ DEAD Ch/CEAO f HIGH RANGE EFFLUENT RAD MONITORS VENT VENT __ 1 PROCESS VENT ) MAIN STEAM A B C , 1 MARKS Annunciator NIs s.a. Less of cetecter veitn=e nese- . l LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - GUENCH SPRAY RSS .- RESERVE STATION SERVICE (A : Ave:1eble. R : Runningb 00C : Out of Commission) PLANT STATUS nEs section to fU NORTH AM4A POWER STATICH $_8'd5 UNIT 1 M MROm0N1 9 o 3 REACTOR POWER 0 % N IMARY SYSTEM d REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH 544 'F HOTTEST TC 543 oF LOOP *1 AT 1 F LOOP '2'AT 1 F LOOP .3 AT i *F' PRESSURE- 2235 PSIG PRESSURIZER LEVEL 16 overfeedine S/cs %- 1 PRT LEVEL 68 % ! REACTOR COOLANT PUMP l A A. (lO 00C B: A. S 00C C: A. M 00C I CORE PARAMETERS l .- CORE EXIT. THERMOCQUPLE 543 'F , .l . MARGIN.TQ. SATURATION Ch A - 108 *F Ch 8 - los F , . . SOURCE._ RANGE. COUNTS N 31 - off N 32 - off ~7 -7 .. . . INTERMEDIATE. BANGE. AMPS N 35 -a x 10 N 36'- 6 x 10 RVLIS loo % , . , , , , , 4 CONTAINMENT TEMP. 97 oF PRESS. 9.9 PSIA SUMP LEVEL 40 % CONT. ISOLATION PHASE I. II. III: HYDROGEN % SECONDA'RY SYSTEM STEAM GENERATOR (LEVEL) A 19 % B w % C 39 % AUX. FEED FLOW 0 (GPM) CN-TK-1/2 LEVEL 99 % AUX. FEEDWATER l 3As A. R .. M _ 38: /A~D R. 00C FV-P-2 @ R. 00C 99 % SI FLOW 0 (GPM) ! ENGINEERED SAFEGUARDS - RWST l HHSI As A. O 00C B: (9 R. 00C C: /0 R.00C OSRS At 4Q R. 00C g:/C R. 00C- ~ ...LHS! A:(O R. 00C B:/O R. 00C ISRS As /$ R. 00C B:TC R.00C .- .QS A /C R. 00C B (52 R. 00C RS-P-3A rQ R. 00C RS-P-3B: M) R. 00C RS-TK-1: a, % , ELECTRICAL DISTRIBUTION EMERGENCY BUS UsUPPLY) , Hi@ DIESEL. DEAD. BACKFEED J@ DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H: OP. Q. 00C J: OP h. 00C RESERVE STATION SERVICE ' A #IOT) DEA 0_ .. B M /DEAO C:@EAre HIGH RANGE EFFLUENT RAD MONITORS f.. VENT VENT ,_, PROCESS VENT MAIN STEAM A B C REMARKS Remove Main Generator Frem service. _ Secure Turbine, Place Steam Dumps in Steam Pressure Mode. ,_ j LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Avellable. R = Running. 00C : Out of Commission) mamy amo _ xea a .- - - _- - s.e n NAEE Section 10 KANT STATUS Pass 30 of 172 , 04 01-85 ICRTH AWA POWER STATION UNIT 1 o .w . MANEUVER OFTION 1 , ( l! MARY SYSTEM 0 REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 547 F HOTTEST TC 547 'F LOOP *1 AT o F LOOP '2 AT n F LOOP "3 AT e CF PRESSURE 2242 PSIG PRESSURIZER LEVEL 24 % - PRT LEVEL se % REACTOR. COOLANT UMP A A. R. 00C 3 A. @ 00C C: A. 00C i CORE PARAMETERS -.. CORE EXIT. THERMOCOUPLE ss2 op .- . . _._ MARGIN TO SATURATION Ch A - lo7 *F Ch 8 - 107 'F " 3 3 . .. _. __. SOURCE RANGE COUNT.S N 31 - 6 x 10 N 32 - 6 x 10 < 10 -11 ~11 . _ .__ ___INIERME0! ATE... RANGE.. AMPS N 35 - < 10 N 36'- - RVLIS too ~% ~ ~' " ~~ CONTAINMENT TEMP- o, oF PRESS. 9.9 PSIA SUMP LEVEL 40 % L CONT. ISOLATION PHASE I. II. III: HYOROGEN % l SECONDARY SYSTEM STEAM GENERATOR (LEVEL) L .A 35 % B 35 % C 3s % . AUX. FEED FLOW n (GPM) CN-TK-1/2 LEVEL oo % p AUX. FEE 0 WATER d 3As A. R. M 38: /D R. 00C FV-P-2 @ R. 00C , ENGINEEREO SAFEGUARDS - RWST 99 % SIFLOW o (GPM) l HHSI A A. 600C B (@ R. 00C C: @R. 00C OSRS A: (O R. 00C g: /O R. 00C l .LHSI A:(O R. 00C B (O R. 00C ISRS As dC R. 00C B: <1Q R. 00C l . . OS An dQ R. 00C B (C R. 00C RS-P-3As /C R. 00C RS-P-38: , MQ R. 00C . RS-TX-1: 97 % ( - ELECTRICAL DISTRIBUTION ! EMERGENCY BUS (SUPPLY) l H@ DIESEL. DEAO. BACKFEED @ DIESEL. DEAO. BACKFEE0 l EMERGENCY DIESEL GENERATOR (EOG) H:OP p .00C i J: OP-@ ,n0C RESERVE STATION SERVICE - A:M OEA0 B716D/ DEAD C M OEAD HIGH RANGE EFFLUENT RAD MONITORS - VENT VENT l PROCESS VENT MAIN STEAM A B C REMARKS commence Reactor Shutdown, boratino to Cold Shutdown with Emercenev , cerate MOV (2200 callons at 50 - @ . Source Range Auto Reinstated. LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC SPRAY QS - GUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Ave 21eble. R = Running. 00C : Out of Commission) ,_ g g7 STATUS. NAEE Section 10 Page 31 of 172

~~5-3/4~~

,_ 7- NORTH ANNA P0wtR STATION 04-01-85_ w wmuvra emot 1 o . R RPM o 'A WIMARYSYSTEMREACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 545'F HOTTEST TC 54s 'F LOOP"1 AT o F LOOP *2 AT o F Loop 13 AT o or PRESSURE 2230 PSIG PRESSURIZER LEVEL 22 % PRT LEVEL se x REACTOR COOLANT PUMP A 4 _ O 00C g A. @ 00C C: A. 00C _ CORE PARAMETERS .. CORE EXI.T . THERMOCOUPLE ss2 'F .. . MARGIN TO . SATURATION Ch A - 107 *F Ch B - 107 'F .. ... _ SOURCE RANGE. COUNTS N 31 - 3x 10 3 N 32 - 3 x 10 3 ... _ . . INTERME0! ATE RANGE AMPS N 35 - <1o'11 N 36 - < lo'll - RVLIS 3nn % , _ , ,, , CONTAINMENT TEMP.- 97 oF PRESS. 99 PSIA SUMP LEVEL 40 % CONT. ISOLATION PHASE I. II. III: HYOR00EN % SECONDARY SYSTEM STEAM GENERATOR (LEVEL) A 35 %B 1s % C " % AUX. FEED FLOW o (GPM) CN-TK-1/2 LEVEL 99 % e AUX. 3As FEEA. O 0R. WATER 38: N R. 00C FV-P-2 @ R. 00C ENGINEERED SAFEGUAROS - RWST 99 % SIFLOW o (OPM) - HMSI As A.@ 00C B: /d R. 00C C: 69 R. 00C OSRS At 4D R. 00C B: #) R. 00C LHSI A /O R. 00C B (E) R. OCC ISRS A: 20 R. 00C B: TO R. 00C . OS As /C R. 00C B:/O R. 00C RS-P-3A @ R. 00C ~~ RS-P-38: (3D R. 00C . RS-TK-1: 97 % ELECTRICAL DISTRIBUTION - EMER NCY BUS (SUPPLY) H: DIESEL. DEAO, BACKFEED J DIESEL. DEAO BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP. M .00C J: OPd. J 00C RESERV STATION SERVICE . A H /0EAD B @ / DEAD C@/0EAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A B C MAftKS sernei m to ceid shuedew . LEGENO- HHSI - HIGH HEAD S.I. , OSRS - OUTSIDE RECIRC. SPRAY , LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A : Ave 11eble. R : Running. 00C = Out of Commission) ~ . _ - . . . . . . . . ,o m. PLANT $7ATUS $ % NO NORTH Meta POWER STATIC 4 04-01-85 UNIT 1 o w N U 4R OPTIC 11 1 h!MARYSYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH sas 'F HOTTEST TC 546 'F LOOP'1 AT o *F Loop e2 AT . o F LOCP 83 AT o or PRESSURE 2:35 PS!G PRESSURIZER LEVEL 24 % PRT LEVEL 68 % ' REACTOR COOLANT PUMP A: A. (19 00C 3 A. @ 00C C: A. @ 00C CORE PARAMETERS ... CORE EXIT .THERMCCOUPLE 553 *F . . _ . . MARGIN._TO..SAIURATION f,h A - 107 *F Ch B - 107 *F 3 3 , _. 10URCE. RANGE _ COUNTS N 31 - 3 x 10 N 32 - 3 x 10 -11 __ ...INIERMEDI ATE._ RANGE AMPS N 35 - < 10 N 36 < 10'11 ' RYLIS ico % CONTAINMENT 97 eF PRESS. 9. 9 PSIA SUMP LEVEL 40 % TEMP.. . CONT. ISOLATION PHASE I. !!. III: HYOROGEN % r SECONDARY SYSTEM STEAM GENERATOR (LEVEL) 34 %B 35 % C 34 % A 0 9' AUX. FEE 0 WATER AUX. FEE 0 FLOW (GPM) CN-TK-1/2 LEVEL % 3As A. R. O 3B: O R. , 00C FW-P-2 4 R. 00C ENGINEERED SAFEGUARDS - RWST 99 % SIFLOW o (GPM) - HHSI A A.TC)00C B: f1tj R. 00C C: @ R. 00C OSRS As '1C R, 00C B: @ R. 00C l' LHSI A:/O R. 00C B: 110 R. 00C ISRS As @ R. 00C B:rC RT 00C . 0S. At l> R. 000 Si @ R. 00C ~ RS-P-3A #) R. 00C ' ~ F:C-P-3B GR R. 00C M-TK-1: 97 % . ELECTRICAL DISTRIBUTION l EMERGENCY BUS (SUPPLY) H @ O!ESEL. DEAD. BACKFEED @ DIEEEL. DEAD, BACKFEED EMERGENCY O!ESEL GENERATOR (EDG) H:OP { KID.00C J: OPh. 00C RESERVE STATION SERVICE Ae(TdDDEAD B: N CEAD Ca k / DEA 0 'HIGH RANGE EFFLUENT RAD MON! TORS VENT VENT ,. PROCESS VENT MAIN STEAM A B C REMARKS . Insert A s a shutdown sank Centrol neds. l Beratine to Cold shutdown. _ LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHS! - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE . (A : Available. R : RunninfhO___ _0C : 0ut of Commission) _ __ __ _. NArt section to PLANT STATUS Pcg3 33 of 172 . ' MlWtTH Amen POWUt STATION 04-01-85 UN!h 1 l 0 * "" ""1 ~ REACTOR POWER 0 % D44RY SYSTEM REACTOR COOLANT SYSTEM (T = Temperature)- HOTTEST TH 546 'F HOTTEST TC s4s 'F *F Loop e2 AT o o p- , LOOP'I AT 0 F LOCP 83 AT o PRES $URE 3339 PSIG PRESSURIZER LEVEL 22 % , PRT LEVEL sa % ! REACTOR COOLANT PUMP 3 As A. dD 00C 3 A. @ 00C C: A. @ 00C ; CORE PARAMETERS l . . .. .. CORE EXII. THERMOCDUPLE 554 *F " , . . _ MARGIN _TO. SATURATION Ch A - 107 *F Ch 9 - 107 'F . _ _ _ _ SOURCE _. RANGE. COUNTS __N 31 2.6 x 10' N 32 - 2.7 x 10' , _. . INTERMEDIATE,BANGE AMPS N 35 - < 10'11 N 36 - 4 10 ~11 ,, , RVLIS too % . , , , , , , , l CONTAINMENT ,F TEMP. 97 ppggg, o o PSIA SUMP LEVEL 40 % . CONT. ISOLATION PHASE !. !!. III: HYOROGEN % SECONOARY SY$ TEM STEAM GENERATOR (LEVEL) ..A 36 %B 36 % C 36 - % AUX. FEEDWATER AUX. FEED FLOW n (GPM) CN-TX 1/2 LEVEL oo % 3As A. R, eM 38: /D R. 00C FV-P-2 @ R. 00C l ENGINEERED SAFEOUARDS - RWST 99 % SI FLOW ^ (GPM) HHSI A A.@ 00C B: r@ R. 00C C (Q R. 00C ~ OSRS A (F)R. 00C_ B: MOR. 00C .LHS! A M R. 00C Be (A) R. 00C ISRS A: (C R. 00C C: ($ R. 00C 05 A:(D R. 00C B @ R. 00C RS-P-3A: 4 R. 00C l l RS-P-3B 4) R. 00C RS-TK-1: M '/. . ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) ' Hi@ DIESEL. DEAD. .BACKFEED J 6 DIESEL. DEAD. BACKFEED EMERGENCY DIESEL GENERATOR (EDG) H:OP h 00C J:OP h 00C - l RESER JVETATION SERVICE A 040I/ DEAD B: M EAD C ( @ EAD I ) HIGH RANGE EFFLUENT RAD MONITORS I VENT VENT . PROCESS VENT MAIN STEAM A B C f *3 MARKS ~--o--. ~ u .u. ,. es' ,er weur, b , LEGENO: HHS! - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY l OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A AvalMInn R : Runnsna _00C : Osq er Cemmaoosen) ,. NAEE Sectira 10 Pega 34 cf 172 nLe 1.n s 0, i 3 i "*N , N e , a .s', i g . . . F o e - ll , 5 1 e, ; h 9 i e . 9 b f / . i I k a O ' m / l 5 / s - [ . / ; -t e N / , i / J f . t

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