ML20063H627

Public Version of Revision 2 to Emergency Plan Administrative Procedure AD 1827.04 Re Overexposure/Internal Combustion & Revision 5 to Procedure AD 1827.13 Re Containment Evacuation.Revision 147 to Procedure Index Encl

ML20063H627
Person / Time
Site:	Davis Besse
Issue date:	07/27/1982
From:	Doyel C, Green W, Murray T TOLEDO EDISON CO.
To:
Shared Package
ML20063H605	List: ML20063H610 ML20063H627
References
PROC-820727-01, NUDOCS 8209020042
Download: ML20063H627 (28)

Text

. . .

THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION E M ONCY PLAN SUPPORTING PROCEDURES

^-

REVISION INDEI PAGE REVISION PROCEDURES REVISION TEMPORARY MODIFICATIONS i 5 HP 1602.01 10 T-6393 HP 1604.01 2 AD 1827.01 3 AD 1827.02 8 AD 1827.03 1 AD 1827.04 2 AD 1827.05 2 AD 1827.06 2 AD 1827.07 2 AD 1827.08 1 AD 1827.09 1 - -

AD 1827.10 12 T-6491 AD 1827.1I 2 AD 1827.12 8 AD 1827.13 5 AD 1827.14 1 AD 1827.15 3, AD 1827.16 1 AD 1827.17 1 1 AD 1850.04 4 AD 1850.05 5 i

ADMINISTRATIVE MEMORANDUMS REVISION No. 37 - ECS Pager and Telephone Numbers 26 No. 38 - First Aid Team 11 l - No. 39 - Fire Brigade 13 No. 41 - Emergency Duty Officer (EDO) 24 No. 42 - Radiation Monitoring Teams (RMI) 16

('

1 7

f' Revision 147

/ July, 1982 8209020042 820813 PDR ADOCK 05000346 F PDR

AD 1827.04 Davis-Besse Nuclear Power Station Unic No. 1 Administrative Procedure AD 1827.04 Overexposure / Internal Cone ==4 nation

, I l Record of Approval and Changes Prepared by C. Dovel/W. Green 1/13/76 Date Submitted by AL3.C9w 2 /is / 7c crion Head Data Eccormended by /ILr ,

'~ ~

SRB Chairman Date QA Approved 4- M -

b 2 '!

V Manage o a114 M surance Data Approved by [ / ((

' Station Superintendent Data

/'

Revision SRB QA Sta. Supt.

, , No. Re ommendation Date roved Date Approved Date f //p //Jgfo  ;-_] 9 3-a.-su 9 f_ _

's//s*/kb 4 ffMJ ^ g'ljs3)r1. Yh'fW# "

l l '

l l

1 AD 1827.04.2

1. PURPOSE

~

To describe the actions necessary to investigate, treat and report the overexposure of an individual at Davis-Besse Nuclear Power Station (DBNPS) due to radiation. Overexposure is defined as any internal or external radiation exposure where the whole body dose - --

is in excess of permissable limits set forth in 10 CFR 20. ,

" ~ ~J. - 2. REFERENCES - ,

2- + 2.1 10 CFR 20, " Standards for Protection Against Radiation" .

2.2 Davis-Besse Station Radiation Protection Manual

[- -

2.3 AD 1842.00, " Chemistry and Health Physics"

- 2.4 . FSAR Section 12

", 2.5 HP 1602.01, " External Personnel Radiation Monitoring"

, , 2. 6 , HP,1605 06, "Whole Body Counting"

~ ~

2.7 AD 1807.00, " Control of Conditions Adverse to Quality" 2.8 AD 1804.00, " Report Management 2.9 TEco NQAM ,

3. RESPONSIBILITIES 3.1 General

~

Each person' who works at or visits the DBNPS site shall

.._ be responsible for complying with the requirements of AD

'1842.00, " Chemistry and Health Physics" for personnel

- radiation exposure. Should any person suspect that he has been subjected to overexposure, he shall immediately notify a member of the Chemistry and Health Physics l

- ' Section.

3.2 ,

Chemist and Health Physicist

., 3.2.1 Conduct final overexposure investigation if indeed it is determined by Health Physics per-sonnel that an overexposure did occur. '

. .*~ '

_' ~

l 3.2.2 Complete " Report of Overexposure Investigation",

(Enclosure 1).

I 2 3.2.3 Submit applicable reports to the NRC as defined in 10 CFR 20.403, 20.405(a), and 20.405(b).

2 AD 1827.04.2 -

3.2.4 Initiate an Action Item Report if required in accordance with AD 1807.00, " Control of Con-ditions Adverse to Quality".

3.3 Chemistry and Health Physics Section Conduct the initial investigation of reports of over-

.. .. - . r

~

exposure to verify the incident and determine the nee'd ~

J. . .. -

for further action and investigation as directed by the - '- - -

. . Chemist-Health Physicist. ~

o- +

.~ . - 4. , PROCEDURE 4.1 External Exposure I 4.1.1 An over-external exposure is defined when it is

_. known or suspected that an individual has been

.. exposed in excess of the limits specified by 10

~

CFR 20.101, an immediate investigation will be

. conducted by Chemistry-Health Physics Section ,  ;

. , , personnel and such reports or notifications as >

_ required by 10 CFR 20 will be, submitted.

.2 -

If an exposure comes within the definition of ._

10 CFR 20.403(a), the Station Superintendent will contact the company's radiation medical emergency consultant for their recommendations.

4.1.2 Routine external radiation monitoring (which ,

will be the indicator 'that an overexposure has i occurred) is described in HP 1602.01, External J Personnel Radiation Monitoring Program. ,

4 . 2. _ Internal Exposure J

.. 4.2.1 If an'over-exposure resulting from internal contamination is known or suspected in excess of the limits specified by 10 CFR 20.103, an investi-

gation will be conducted in accordance with HP 1605.06. .

. 1. The services of the company's radiation medical emergency consultant may be utilized to determine the magnitude of any excessive -

exposure, its cause, and effective preventive

- - - .. . - ~ _.3...__.,-- measures. - . -

2

2. If the amount of radioactive material in the body exceeds 10% MPOB, a dose assessment should be performed.

4 .*

a

3 AD 1827.04.2

3. If there is a reasonaole probability that any individual incurred an internal deposition of ,

2 one or more radionuclides exceeding.520 MPC-hours the Station Superintendent will contact the company's radiation medical emergency consultant for their recommenda- - --

tions.

~

4.2.2 Routine internal monitoring of contamination s - -

(which will detect if an over-exposure resulting r from internal contamination has occurred) will

. L. ,

be performed as described below.

.~ Whole Body Counting

1. Yearly whole body counts will be taken on

, . selected station personnel.

2. Selection of the individuals for whole body counting shall include at . east 25% of the '

personnel assigned to the station.,

~

3. Criteria used for selecting individuals will be quarterly whole body exposure records and work history in airborne radioactivity areas.

Tritium Monitoring

~

1. Urinalyses for tritium will be performed for selected station personnel.

. 2. On a quarterly basis, a bioassay for tritium

?'

~

l will be collected from individuals who have

. been working in areas where there could be a potential for inhaling tritium.

NOTE: During periods when the Refuel-ing Canal is filled, urine

_. samples for tritium should be collected from selected indi-viduals every two (2) weeks.

4.3 Records 4.3.1 If the limits specified in 10 CFR 20.403, .405,

-" ~_ . . _ _ . _ have been or are.likely to be reached, the' ~'

Region III Director of the NRC shall be noti-l fied.

l i

s

4 AD 1827.04.0 -

4.3.2 The Chemist & Health Physicist shall be respon- ,

sible for initiating the Report of Over-Exposure form. , i M

..- e- -

S. -

S 4

s y " @& e g

p

' 1 A

e

~~

-. 4

~'

e.o eq l .

t 1 ... .

G #

1 . .

t I

, r- f'_-..,..... -- .'. _ ,

e i =~.

I l

i

5 AD 1827.04.0 -

i REPORT OF OVEREXPOSURE (Over-exposure resulting from internal or external radiation exposure) .

Name Date i Soc. Sec. No. Job Title - -

.- ....Date. &. Time qf Possible Overexposure

,. Eocation Expo'sure Occurred

.- +

.'.J. REP No.

~

. Type of Work or Operation at Time of Exposure

~

.. . ~

.. - How did Exposur_e_ Occur r

Why did Exposure Occur <

i l

Was Employee Injured Yes No Describe l Medical Treatment Required -

- i l

i-i

, .- t Damage to. Equipment-  ;

I Type of Exposure Involved:

Whole Body Other -  !

. . Skin '

Radionuclides Hands & Forearms

--- r-Feet &- Ankles _. ._., - -

_i Internal

- Survey of Exposure Location: By Title i t

Gen. Bkgd. mR/hr Hot Spot (s) mR/hr

~

L Enclosure 1 i Sheet 1 of 3 l c

6 AD 1827.04.0 Air Activity pCi/cc Hot Spot (s) mR/hr ,

Contamination: Surface dpm/100 cm2 Dosimeters Readings mR-Ser#

- - 6 mR-Ser#

.. .. . )

. . . _ Evaluation of TLD: Beta -

mR .

.> Gamma mR

.~.., , .l Beta & Gamma mR

--]

i

- Neutron Exposure e l

. Were Nasal Swipes _Taken Results Was Sputum Analyzed Results  !

Was Whole Body Counten Utilized (Attach scan to'this report) '

J'

~

Bioassay Program Begun Final Disposition:

Did overexposure occur Yes No (If yes, initiate NCR)

)  ;

Total Dose Assigned for Period to >

liholeBodykExternal)

?>

(Internal)

Jl ll Skin -

Extremities Other T-

-r Future Radiation Exposure limitations .

Future Clinical Radiation Data Required i

• - . . - . -

• i _-

?

-[

l From Title 10 CFR 20 " Standards for Protection Against Radiation"; -

20.403 and 20.405 - is an NRC notification and report to Regional i Compliance Required I

Yes No  !

l  ?

Enclosure 1  :

' Sheet 2 of 3 i.

! 4

7 AD 1827.04.2 2 Has 520 MPC-hours in a 13 week period been exceeded?

Yes No If the answer to either of the above questions is yes, contact the company's radiation medical emergency consultant, and complete report - -

NP-02 as required in accordance with AD 1804.00, " Reports Management",.

....~ . _-- . .

- ; . NRC Region III Telephone (Days, Nights, Sundays & Holidays) - 312-858 .2660'.

~

2- ,Who made telephone call Time Date

~6- .. .

To whom call was made Capacity-

~

, , .Date and Time of Telegram Confirmation

, .,._ To whom telegr.am sent Capacity Date and Time 30 day written report mailed To whom report sen,t Capacity -

Was report Mailed Registered Return Receipt?  !

t (Attach copy of report, telegram statement, and phone conversation to this investigation.)  ;

Signatures of Personnel Making Investigation:

~, :.

d ,

. 4 Name Title Date  :

~

Name Title Date Name Title Date Chemistry & Health Physicist

- w --

_. Signature _Date l Station Superintendent Signature Date

~

Enclosure 1 END ' Sheet 3 of 3 4

0

-. AD 1827.13 .

Davis-Bossa Nuclear Power Station Unit No. 1 Administrative Procedure AD 1827.13 Containment Evacuation l

l

~

I,-

l J,a

.,g Record of Approval and Changes Prepared by R. P. Wachen/W. H. Green 12/30/75 l Date Submitted by . I) . @ $. h ~,s d /6 / 7 G Section llead Date Recommended by O '-, 4 ['7C SRD Chair 6an 'Date QA Approved NA SIA 8 -.

Mana r - QuaIfty Assurance Dat Approved by A ~

O

~ Sitat1on Superintendent 7Date/

?,

Revision SRB QA

• Sta. Supt.

. No. Recommendation Data Approved Date Approved Date j && 4/4'77 jo.f -B'hrp%/ser  !

3/"/as

)

h / W f Q C ^ = --g '/l'7/80 BIsjtl

e. a C

no _ _ g alic. lao

{ LLC /f/ WWU = . V)%lEl p e_y., 3 3lsup; C- Q n/affri w /yv - -_

s.l > 'o th p g _ -- _ 7[,2l rd Wh/S)d.JdMfA D # " ^Jr 7 " #~' -

,._m. _ _ _ . _ . _ _ . - . . - . . - . - _ . . _ _ _

1 AD 1827.13.4

1. PURPOSE & SCOPE ,

This procedure sets forth the actions and measures which assure that Containment (the area enclosed by the Containment Vessel and the Shield Building) is safely evacuated by station personnel working inside, in case of emergency, or increase in radiation levels in Containment beyond allowable levels. The procedure further describes actious which assure that decontamination of exposed and contaminated personnel, is accomplished.

2. REFERENCES 2.1 10 CFR 50 Appendix E, " Emergency Plans for Production and Utilization Facilities" 2.2 DBNPS-FSAR, Appendix 13D, " Emergency Plan" Section 7.8, " Nuclear Instrumentation" Section 11.4, " Radioactive Waste Monitors" Section 12.0, " Radiation Protection" 2.3 SP 1104.21, " Containment Purge System Procedures" 2.4 SP 1104.41, " Containment Vessel Hatches" 2.5 MP 1402.06, " Equipment Hatch Removal and Replacement" 2.6 HP 1601.01, " Guides and Limits for Exposure to Radiation" 4l 2.7 HP 1601.04, " Radiation, Contamination and Airborne Radio-activity Areas" 2.8 HP 1601.03, " Radiation Exposure Permit Procedure."

2.9 HP 1602.01, " External Personnel Radiation Exposure Mon-itoring" 2.10 PT 5179.01, " Area Radiation Surveys" 2.11 PT 5179.02, " Contamination Surveys" 2.12 PT 5179.03, " Airborne Radioactivity Surveys" 2.13 HP 1604.01, " Personnel Decontamination Procedure" 4l 2.14 AD 1827.11, " Station Evacuation"

- 2.15 AD 1827.12, " Protective Action Guidelines"

3. ORGANIZATION AND RESPONSIBILITIES 3.1 Working Personnel _

2 AD 1827.13.2 Containment evacuatioe is the responsibility of the personnel working inside the Containment. The personnel ]

in the Containment shall take prompt action to remove I themselves from Containment whenever the Containment Evacuation Alarm is sounded or their personnel monitoring '

equipment indicates that a dose limit has been reached or l an excessive level of radiation or airborne activity exists. ..

l 3.2 Shift Supervisor 2 ,

The supervision of the control room operation, par-  !

ticularly as regards radiological monitoring during work i in Containment, is the responsibility of the Shift Super-visor. He shall evaluate any changes reported by the i Control Room Operator (CRO) and the Chemist and Health .i Physicist (C&HP) in order to coordinate emergency activ-ities relating to the evacuation of Containment. He is ,

responsible for keeping the Station Superintendent 'j informed of emergency conditions and announcing the location and nature of emergencies over the PA System. .a 3.3 Control Room Operator -

The constant monitoring of radiation conditions in Con-tainment is the responsibility of the CRO, particularly -

when personnel are working inside containment. He shall evaluate changes in radiation levels detected by con- i tainment atmosphere detectors as well as out of core j neutron instrumentation in order to be able to signal evacuation.

I 3.4 Work Supervisor / Foreman

_, The leader or foreman of each work group present in U 3

Containment shall assure the evacuation of sny or all -

personnel upon hearing evacuation alarms, or upon per-sonal verification that excessive radiation levels exist. ,!

The working supervisor will normally be the last man out a of Containment.

3.5 Chemist and Health Physicist (C&HP)

The monitoring of radiation dose and exposure for all i personnel working in Containment is the responsibil'ity oi  !

the C&HP in accordance with HP 1602.01, " External Per- "

- sonnel Radiation Exposure Monitoring". As part of the i personnel monitoring program, REP and personnel dosi-meters are issued by the C&EP to all personnel entering -

Containment in accordance with HP 1601.03, " Radiation Exposure Permit Procedure". .

_ 3 AD 1827.13.5 The C&HP will not monitor or check containment during reactor operation due to the high neutron and' gamma radia-tion levels. With special permission of C&HP management, entry can be made into containment for very short periods of time, according to the FSAR, Section 12.0, " Radiation Protection", to evaluate containment radiation levels in accordance with PT 5179.01, " Area Radiation Surveys",

i PT 5179.02, " Containment Surveys," and PT 5179.03, " Air-borne Radioactivity Surveys".

The C&HP is further responsible for the monitoring and/or decontamination of personnel after evacuation from Con-tainment in accordance with Section 12.3 of the FSAR, HP 1602.01, " External Personnel Radiation Exposure Mon-itoring", and HP 1604.01, " Personal Decontamination Procedures".

)

4. CONTAINMENT ACCESS The following paragraphs describe the accesses to the Containment which may be used for evacuation with the limitations as noted.

I 4.1 Personnel lock - Elevation 603, southeast side of Con-tainment. This is the normal access for personnel enter-ing and leaving the Containment during operation and

. shutdown. The lock area has room for about ten persons with an automatic pressurization and purging system.

Ref: SP 1104.41, " Containment Vessel Hatches". (See 5 Enclosure 1).

4.2 Emergency Lock - Elevation 585, northwest side of Con-tainment. This exit is a 5' diameter pressurized vessel for emergency access only, for personnel working.at level

• 585, and for personnel working at lower levels during shutdown. The lock area will facilitate only 2 or 3 personnel since the access doors swing inward. (See Enclosure 2.)

4.3 Equipment Hatch - Elevation 603, southeast side of the Containment. This hatch can be used for evacuation only during reactor shutdown when the hatch has been opened for equipment handling. The hatch is normally secured and locked and is removed and replaced in accordance with l MP 1402.06, " Equipment Hatch Removal and Replacement".

(See Enclosure 1.)

4.4 Mechanical Penetration Hatches (205A & 201B) - Elevation i - 565, east and west side of the Containment and (308A &

l 307A) - Elevation 585 - southeast and southwest sides of Containment. (See Enclosure 2 and 3). These doors l

I 1 , i 4 AD 1827.13.4 provide access and exit to and from the annulus area only ,' '

but do NOT provide access to the containment vessel, and  !

are normally secured and locked. During shutdown or  ;,

, emergencies, these doors may be opened for access and i shall be used for evacuation from the annulus area during ,

these periods. Since the annulus may be a high radiation  :

area during reactor operation, these doors can be opened only in emergencies and for short periods after purging ,

in accordance with SP 1104.21, " Containment Purge System Procedure".

5. EVACUATION ALARM AND PROCEDURE t

5.1 Alarm Criteria 5.1.1 Manual System The control room operator shall monitor con-

, tainment radiation instrumentation at all times ,

during reactor operation as described in the l FSAR, Section 12.0, " Radiation Protection",

I whenever personnel are in Containment. He shall -}'

4 initiate the Containment Evacuation Alaen and announce verbally the extent of evacuation .,

required when the following symptoms are veri- l 4 fied: -J i

o Alarm for high gamma radiation on any con-tainment radiation monitors. j, o High count rate in the source range instru-mentation , ,

o Increasing count rate (3 dpm) in the criti- ,

.. cality monitoring system during startup

(refueling only) o High radiation level in the gaseous / airborne monitoring instrument in the containment ventilation system.

4 NOTE: Operator needs to verify that the readings are valid before evacua-ting Containment. Setpoints will vary with plant conditiohs and age.

. 5.1.2 Automatic Alarm System f

The affected radiation monitor will automatically sound an alarm outside the entrance to the per-

_ _ _ . _ _ _ _ . ~ . _ . . . _ _ . _ . . _ _ _ _ _ __ __.._ _. ._ _ _ . _ _ , . _____ . _ . _ _ _ _ .

t 5 AD 1827.13.4 sonnel hatch or outside the entrance to the equip-ment hatch. The Control Room Operator will receive an alarm at the FDS/RMS Console CRT and Printer.'

The monitors also provide a readout in the Control Room and at the personnel / equipment hatch entrance for verifying conditions.

5.2 Personnel Evacuation Procedure 5.2.1 Upon hearing the Containment Evacuation Alarm, personnel will immediately lay down all work equipment, secure, open, or close any critical switches or valves and proceed to the personnel lock at level 603 and/or evacuate through the equipment hatch at level 603, if open. (See Enclosure 1).

5.2.2 Evacuation will commence immediately through the personnel lock which will be operated in accordance with SP 1104.41, " Containment Vessel Hatches".

5.2.3 The foreman / leader / supervisor present in each work group shall assure that his personnel have been accounted for and/or entered the personnel lock before the inner door is closed and secured. He shall leave Containment only when all of his personnel have been accounted for.

5.2.4 Upon exiting the personnel lock, all personnel shall proceed immediately to the Disrobing Area for a contamination check in accordance with HP 1602.01, " External Personnel Radiation Exposure Monitoring". At this time, the foreman / leader shall notify the control room by phone that Containment has been evacuated, and to await action by the C&HP personnel regarding their exposure and conditions in and around Con-tainment.

5.2.5 The emergency lock at level 585 may be used for evacuation only if the route to the personnel lock is cut-off or impassable. Procedure for use of the emergency lock is also described in SP 1104.41. Personnel exiting by the Emergency 4 Lock should stay in that area until released by C&HP, notify the Shift Supervisor of their t

. evacuation and the conditions inside Containment.

! (See Enclosure 2).

1 i

5.3 Control Room Action

6 AD 1827.13.2 l

~,

5.3.1 The control room operator monitoring an unsafe '

condition in Containment shall: 7

-l

1. Check the instrumentation readout (s) for supporting evidence of the condition. 7

2. Check the alarm for failure.

3. Upon confirming the emergency condition, initiate the Containment Evacuation Alarm.

5.3.2 The control room operator, after the evacuation l alarm sounds, shall take immediate action to correct the situation, reduce the radiation levels and restore the station to normal con-2 .

ditions in accordance with the Emergency Imple-  ;

menting. Procedures, EI 1300 series.

1

~2 5.3.3 Notify the Shift Supervisor, Station Super-intendent or his designee and/or the EDO of the evacuation and reasons for the alarm. _.

5.3.4 Log all data pertaining to the evacuation includ- '

ing the reports verifying evacuation of affected personnel and conditions inside Containment.

5.4 Shift Supervisor Action 5.4.1 Verify the conditions reported by the control j room operator and announce the emergency over the PA System.

2 NOTE: Check Emergency Plan Activation, EI "

1300.01 to ensure the proper emergency ,

_, classification and the actions accord-ingly.

5.4.2 Determine if it is necessary to evacuate ,ther l areas of the station in accordance with AD .;

1827.11, " Station Evacuation Procedure".

5.4.3 Ensure that no one re-enters Containment until it has been determined safe by Chemistry &

Health Physics personnel.

)

5.4.4 Coordinate and monitor station recovery activity -

.2 in accordance with the Emergency Implementing Procedures, EI 1300 series, and applicable operating procedures and assure that conditions are restored to normal in Containment.

7 AD 1827.13.1 5.5 Action of Radiation Monitoring Team 5.5.1 Report to the Health Physics Monitoring Room for instructions.

5.5.2 Survey area immediately adjacent to the Con-tainment personnel loch and other areas which were used for evacuation as determined by the EDO and/or C&HP.

5.5.3 Check evacuated personnel for contamination in accordance with HP 1602.01, " External Personnel Radiation Exposure Monitoring," and decontami-nate, as necessary, in accordance with HP 1604.01, " Personnel Decontamination".

5.5.4 Report results of surveys and personnel mon-itoring to the C&HP or EDO and the control room for evaluation.

l i .

e

- --- w- m--, - _ -- A

8 AD 1827.13.5 CONTAINMENT AND AUXILIARY BUILDING ELEVATION 603' NOTE: The Equipment Hatch shall _

l be used only when opened fo maintenance during shutdowr.8 N .

. y

,i summa 1- .

mm--- ,

t

\,

1

!(

D

.'- l  !  !

\  :

I i

b. .

h 1

'l

\r -N -

~ -

1 e s \ i A_ -Ir.

l

\

. \ \ m q

f. },

" l. l' 'Pusoud i

i" l

j. Lock j,

{.

t ww.-w

[ _b -

I i l l

l  : Equipnent i N ,

l

[

Hatch .

-l l L h- _

.I ;

.. L

~C  ?, 1 I g' '

R:

~

,ur_.c...u _ r. - . . : .,_..4 m , -.i _

u -

ll t, ca s. - - -

43

,........a

~ . 1 '

_.G

.__ ITiiii il 11L.J

) :_. -

1 5 j T

n .

_,,_._  ?

I f

o. . . . . .

._.., Decon. Area )

• _s i

I l g

, e

"" '~

I. litillitil $

.b a - -_ . . _s . , - - _ _ :,.__ _ _ x , ,_ .

m. ,__

1 It'lll'8'  ! '

~ ~

I ENCLOSURE 1 i

I I

9 AD 1827.13.5 CONTAINMENT AND AUXILIARY BUILDING ELEVATION 585'

- PRIMARY EVACUATION ROUTE:

[ .

fr Use stairs up to Personnel Hatch at 603' elevation.

. I \ Emergency Hatch (Secondary T Evacuatinn Dm" M i

i% . [#

N

. . mw_ ~ =?m m _2 i

!>r -

1  ! -

k . i i

p<1 , - ,

H ..

. = .

f a.m - a w w_ ,

,; C .

j[ a#3 Mech-nical Pene-g ,

~

p g -

, trucion Room 2 Annulus Penetra- &mesmo g i

?- --

tion #4 Mechan- 1 3 M ical Penetration ]

Room Annulus Penetrati 1

{ ,

q i .__ _.__ .__ _

a" e r F

i --

-gr,978 2 21.'<.'**

lc fill *HMII3 @ - .

X  !

e w  ;  ; -

g s

y e l k a

3 p

b

{

[ E

• ll 2 2

.D -

I i I

l_- )

l12 m . 1 g >

n WWW4i@ . . . ~. % N - --

~

ft _. , _ .__ __

E ENCLOSURE 2

10 AD 1827.13.5 I

CONTAINMENT AND AUXILIARY BUILDING

. ELEVATION 565' ,

! j

• L . -.

,l p - -

( t

l t

)

i

~ .

f!

.' - . L:

Annulus Penetra- . t!

i

' tion N

- o g A) .

~ -- .

i

y, p

E N

- El t

'hn.ulus .-

e sw, .-- -_c.,-,=..- -

j

(

W Pen

• ration '

~

di Mec anical

]

w 34ig; i

f a

- j enetv-H - -

• jj mz, -_ _ _ - - . & . Room l l ,

8, L .

IEl b f

l g S

Q. ~j#1Mechanica

' -m- - - .

g I

f!

Ii 0 s 'hi g Penetration Rm. S' 5

.4 '"

l;;;2ll$ \ --

i

, /

/ t b l

[l l _mmy_g--.g gg%yj3

!l m -

j p& p .\

l t

g atj f ..... -  ; g, r:

{

{_lillis 1

---

- - - ~ _

5 m y i a iW W f I

• bi l ..?  :

y . __

-_1_y

' *

• O

^ 7,^ , ,

mzw=& n,, uu~.:

/4 ELJ.VATC PLATF M ,,

t

~ '

ENcLosuas 3 .

i 1

i ST -

l r

i l

O I;UTIO N Original, Rosseneitse Section Hessi Astion Pile Copy, Meneer Flie

[pff/

COPIES TO BE MCDIPIED POR IMMEDI ATE IMPLEMENTATION

..., DAVIS 8 ESSE NUCt. EAR POWER STATION . UNIT 1 g$ , y,, j,' ; ,

^ ggg ,y,,

TEMPORARY M00lFICATION REQUEST t o 2.

W*' Wi Aaa Adk-2. y SECTION 1 PROCEDURE TITLE AND NUMBER O Yt s k ~

AJ  ?

M. tW' l'E ASON PCR'CH ANGE I eY b U O'

}f [., .

nee w /yh /d a .a~ w > ff g & eo u/e d upY caw c 4 pp3.

CHANGE h3 e azia.6/ p p>>

IS PROCEDURE REVISION REQUIRED PREPAR j DATE f , */

9/V/t's TrLet l /h t.+ . ) DATE APPROVEQ SY ,

[ ,

APPROVEQ SY I '/ / ,, DATE ,

, /_ a

-) s s>_,r> * . W.=*

DATE SUSMITTED BY (Section Hons) ,

A_ ta dud c' '7 / m / R 2.-

RECOMMEN Chairmen DATE QA APPROVED 8 fueneger uailty Assur el DATE *

! / /

APPROVED SV (State Suourintenosat) DATE (l ,hY W'W~ v

, '? />3 /Pt

• t.

26 AD 1827.10.11 /

Instructions For Accessing DEC PDP 11/03 .

For Meterological Data .

\

1. Turn phone accessed data terminal on. *

2. Ensure unit is in ready mode (Press the LOCAL / TALK b ton on Model 43 terminal).

3. Check three options: '

a) ' PARITY - off i i

b) \ DUPLEX - full

• c) \ BAUD - 300 or 30 CPS ' ' *

.x.

4. Dial phone number 898-6240 (Oak Harbor) When the frequency tone is heard, press the DATA button on Mo 1 43 terminal or insert rocciver into the acoustic coupler o other models.

\

5. Correspondence etween Computer an Terminal Operator:

a. Compute will type: WHO ARE YOU7 .

b. -Typc in: .. . t (an up arrow)

c. Computer will pc

!! = 112, M = MIN, C = CAL,

d. Type in: ..  %

H. M, or C (Type only one for either hourly, minute or cal-ibration. check) ' .

. Type "M" to. request da Q;,,by, hourly inperv

,' . specified.... ,t,8.,als,

.J- .. for. the , f '.edate .'

s ; *. 'ry ' >

' . . :st.. & .,.

e', '? r. ~*

). *':

. , 'r

. c Ty a. "M"

'. by!!S to requestfor

'? " min te' intervals, data',.l,date

.the specs, ied.'-

• y *. .- ..

Ty'pe "C*sto request calib' ration

, check (not\normally used)

a. Computer will type ACCESSED COMPUTER.

K '.

• TYPE JULIAN DA REQ. -

f. Tygur in: Theco digit Julian aLo (e.g.

001, 072, 365) g.. Computer will print TRANSMISSION COMPLETE.

out data esquestcu and ALL DONE7...Y or N then typc: '

.,I

{

i;N Attachment 2 '.

Page 1 of 3 .

27 AD 1827.10.11 *

. .t -u P ins t, e;- N (if mora @ta. ^ . ed, then

. s .

Proceed th s,te.ps c g again),

or  :; ,, -

.e. . .o I- TYPO in:

if no [h$br .

~

data is needed)

J' -

. Computer will type: rvnwTv G CbMADlICATION. ,

GOOD DAY

. h a up the ne and turn the terminal..o,ff, as ..

uired.

n.a ,- -

+y6

/ -:.C]

. M.* .

i. . .

. . - . -l , .*'.y .. . .. :. : . ..

.s  ;. -

a -

is .. e.

,u .

. ,i.t ;.* ... .

y ,-t.-

. n '.'

.-  : s; ,p t- ,

. . .o .

t.

.gt t . .. .} .** .. e 4.,. .. ....c. .

. ..v

, ,~.-

. a.. .,

.e

.et. - . m.%..

~ '

e. .. .. . .,>

=

i.

.- ~..w a. . - a. .

. *gq #e .

t a .

c. .

,0.'. g .-

q,: '

f. .

),. ,.. ~ ' .

1 t.- g

't -

9 r ' .

3 * .

Accachment 2 Page 2 of~3

. /

~ '

, ,' t

. 28 AD'1827.10 11- i s '

• .. g Sample Output of Meteorological Data N g s

(While Accessing DEC PDP 11/03) ..

g- ' yp

. k. r.

?

T h- t

N' f4r#'fechnical Specification 4t3.3.4 i; ' .;

f,;j.-

, Elev 821' wind spee Elqv 821' wind dipection Elev'612' wind sfeed . .

VV Y Elevc'612' wind rection 4 Elevj821'-612 tempe'.rature differential REV2 <--1004--X- 54--X---10n---X100RX75MX-TEMPER UEE-><PREXSSSDDADS HRanN US UO SD US SD US US SD DT- DT Ans 10 U IUDU CIP DDDFFPun 1 27.7 2. 24.4 3. 13.0' 7. 0.1

• 30.4 l'5. 4 1 0 195. 202. 194. 0.0 1 1. 7 '.* 0.00 1 0.

2: 24.0 2. 23.4 2. 12.4 7. 0.3 3 .0 17.0 1 0 I??. 204. 174. 0.0 13.4 0.00 1 0 3; 25.3

~ 2. 21.7 2. 1 4 7. 2.0 al.7 18.Y 1 O 230. 213. 74. 1 15.5 0.00 1 0 -

4 27.4 3. 24 4 3. 13.7 4. 0.5 35.8 17.7 1 0 220. 227. 21 .4 17.5 0.00 1 0 5; 33.'O 3. 27.? 3. 17.5 -0.1 37.1

• 20.7 1 0 i 221. 228, 216. -0.0 17.5 0.00 1 0 6: 32.2 3. 27.2 3. I8.5 5. o3 37.4 23.4 1 0 -

222. 230. 217. -0.I 22.5 0.00 0 34.3 ,},

7; 3. 31.5 3. 22.7 4. 9. 37.7

• 24.3 ' ,1 0 s 230. 238. 227. 0.5 25.8 0.00 1 0 1; 31.4 3. 27.0 3. 20.7 4 -0.4 34. 4 .. 28.2 1 0 234, 245. 235

.0,. - 28.0 -

0.00 , I 0

?; 31.3 3. 27.0 .

3. 21.2 4. -0.5. . .

35.3 28f 8 .  : 1., . . 0-241. '

250, 2

~

. -0.3 .

28.4'h ;,;"l 0.00,:j. . . 21

• 0 ;.J.

los 27.2 4, 27.4 .:. 29 5 " 5. -l.l* v* .'i3t 2 p,2P.1 ... - .og;;

245. **

27.2 254'.* s 3, 25.4 4. 1 .2.

255. *

-0. 0 ". 28.7'..o.0.40J..

• 1.,1, 0 ,, ,

7 lia 5. '-l.2 .

"35.0- 4 2%1': 1  :.e -

254, 244. 25.4. -0. 8' - h .'7.e ' i,'0)' C0 20.0 4. 24'.7 1' 0:.9.*

' 12;

4. 21. 1 - '4. -1.2 ' 3 4 .,2 .261 '

.-lN 1 'C 248. 257.

,',244. -0.7 (f.,28,.4. 0.00 .,,t h

. f.ECEND

• b .

h(?,'"

g ..

. . . . .t .s

• . ;d . Q' .

a .,.:g ..

11R:t1N hour, minute (Eastern Standard ,'

NOTE: ... . Data for P.11/03 is Time)/

• read from e' He t;.. Tower IOOH 100M olov (917')

/Lil 75M c' icy (821') and stored- r. t.licce days only.c McL Tower luti lotVolav (612') ia down, only wuvLous W4 wind spcod (MI'll)

Wu ind direction (dcgrecs) information cag bc SD accessed. N standard deviation '

DT -

differential temperature 'F amb DW ambient dry bulb temperaturc *F dcwpoint temperature *F

(

precip precipitation Attachment 2 E,{!D, Page 3 of 3

liintrucLAuna l'or Accus ing DEC t'Di* 11/34 For Meteorologien1 D'.tn

1. Turn phone accaseed duca terminal on.

2. Ensure unit is in ready mode (LOCAL button on)

3. Check the opcions:

a. PARITY - off

b. DUPLEX - full c.

BAUD - 300 or 30 CPS.

4. Dial phone number: 2379. When the frequency tone is heard, press DATA button. Hang up phone receiver.

5. Computer / Operator correspondence:

a. Computer will type: > '

b. Operator will type: HELI 4 100,100 Return carriage

c. Compuccr will type: PASSWORD:

d. Operator will type: (Rafer to memo dated July 1, 1982 from Jennifer Scoct-Wasilk Jor the appropriate password)

Return carriago NOTE: Password will not be printed

e. Computer will type:

RSX-11M BL26 MULTI-USER SYSTEM COOD AFTERNOON .

08-JUL-82 13:23 LOGGED ON TERMLNAL TIl0:

Toledo Edison Company Davis-Besse Site Environmental Monitoring Computer System UNAltIHORIZED ACCESS I.YIO THIS SYSTEM IS PROHIBITED BY FEDERAL LAW NOTE: The system cimo on this computer romains at Eastern Scandard Time the year around.

>6LOGIN.CMD

>SICI / SLAV =TI:

>; DAVIS-BESSE WEATHER DATA

>RUN SURVET SELECT OPTION 1 - DISPLAY HOURLY AVERACE WEAIHER DATA 2 - DISPLAY 15 MINUIE AVERACE DATA -

3 - LIST WEATHER TOWER GENERAL LNFORFATION 4 - LIST DEFINITIONS OF WEATHER DATA ABREVIATIONS OR CARRIAGE RETURN TO LOG OFF

PN ENTER OPTION (1, 2, 3, or 4):

f. Operator will type: (Enter opcion of your choice)

Return carriage NOTE: Computer is on EST

g. For Option 1 Computer will type: Please enter the starting acnth, day, and hour you wish to look at or RETURN to return to

,opcion list (MM.DD.HH, or RETURN)

Operator will type: (Entur month, day, and hour of your choice.

Return carriago Example: 07.08.10)

Computer will type: Please enter the ending month, day, and hour you wish to look at (NM DD HH):

Operator will type: (Enter month, day, and hour of your choice.

Example: 07,08,15)

h. For Opcion 2 Computer will cype: is the current time (EST). Any hours you ask for which are greater than this hour will assume to be hours which occurred yesterday.

l A total of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> worth of 15-minuta average i data is available.

Enter the scarring and ending hours (0-23),

or 24 to get all 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, cr RETURN to return to option lisc [SHR, EER, or 24 or RETURN):

1. Computer will print out requestod data and return to option list J. If more data is required, ropcat stops f - j.

k. If you wish to sign off, push RETURN and computer will print:

> SET /NOSLAVE=TI:

> BYE TASK "...AT." TERMINATED ABORTED VIA DIRECTIVE OR MCR AND WITH PENDING 10 REQUESTS HAVE A GOOD ATIERN00N 08-JUL-82 13:25 Tr10: LOGCED or/

1. Push TERM READY to return printer to a stand 'wy cwudition.

. _ . =-_-_-- - _ -- -_ -

DAVIS-SESSE SITE WEATHER DATA m HOURLY AVERAGES 7/ 9/82 100 nETERS 75 nETERS 10 METERS 100 75 AnB 10Du HOUR WSPD UD/SD WSPD UD/SD USPD UD/SD DT DT TEMP PNT RAIN I S.8 339. 8.0 337. 4.1 324. 1.2 1.0 72.7 69.4 0.00 3.0 4.0 5.0 2 Y.4 342, 9.2 343. 5. 4' 333. 0.1 C.4 72.2 68.0 0.00 5.0 6.0 10.0

~

3 Y2 346. V.0 348. 5.4 340. -0.8 -0.4 71.7 67.5 0.00 3.0 5.0 Y.0 4 10.0 348. 9.9 347. 6.3 338. -0.5 -0.1 70.9 22.4 0.00 3.0 4.0 17.0 5 11.1 349. 10.9 348. 6.3 339. -0.4 -0.0 49.7 43.1 0.00 6.0 7.0 10.0 6 8.9 5. 8.8 3. 4.4 355. -1.2 -0.9 70.4 65.3 0.00 4.0 3.0 8.0 7 U.8 7. 8.3 7. 7.4 3. -1.5 -1.2 74.8 65.4 0.00 7.0 7.0 12.0 8 Y9.Y 999. 99.9 ,999. 99.9 Y99. 99.9 99.9 999.0999.0 0.00 esse see. ....

l l

~

E 1

4

'N METEOROLOGICAL PARAMETER ASREVIATION DEFINITIONS USPD -- Wind speed an n11os per hour. WSPD's are given at the 100 neter 75 neter, and the 10 neter levels.

WD -- Wind direction in degrees, north = 0. WD's are given at the 10 0

neter, 75 noter, and the 10 noter levels.

SD -- Standard deviation (signa theta) of the hori:ontal vand direction SD's are given at the 100 neter, 75 noter, and the 10 neter levels 100 DT -- Tenperature differential in degrees fahrenheit between the 10 0

noter and the 10 noter levels.

75 DT -- Tenperature differential in degrees fahrenheit between the 7 5

nwter and the 10 noter levels.

AnD TEMP -- Tenperature in degrees fahrenheit at the 10 noter level.

10 DW PNT -- Dew point tenperature in degrees fahrenheit at the 10 note e

lovel.

100 DU PNT -- Dew point tenperature in degrees fahrenheit at the 10 0

l noter level. 100 DU PNT's are only available for 15 nanut e

averaged data.

RAIN -- Precipitation 1 taches (down to 1/100 of an inch) at the 1

noter level. Precipitation is never averaged, anstead, it i s

totalled.

l

=

e ,