ML20094N555
| ML20094N555 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/20/1984 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16341A200 | List: |
| References | |
| DCL-84-268, PROC-840720-01, NUDOCS 8408160273 | |
| Download: ML20094N555 (138) | |
Text
_ _ _ _ _
i PGandE Letter No. : DCL-84-268 CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A TITLE REY OP-0 Reactor Trip With Safety Injection 6
OP-1 Loss of Coolant Accident 7
OP-2 Loss of Sec9ndary Coolant 2
OP-3A Steam Gen Tube Failure 5
OP-38 Minor Steam Gen Tube Failure 1
OP-4A Loss of Electrical Power 1
OP-5 Reactor Trip Without Safety Injection 5
OP-6 Emergency Boration 6
OP-7 Loss of Condenser Yacuum 2
OP-8 Control Room Inaccessibility 8
OP-9 Loss of Reactor Coolant Pump 4
OP-10 Loss of Auxiliary Salt Water 2
OP-11 Loss of Component Cooling Water 3
OP-12 Melfunction of Auto Reactor Control System 1
OP-12A Failure of a Control Bk to Move in Auto 2
OP-12B Cont Withdrawl of a Control Rod Bank 3
OP-12C Cont Insertion of a Control Rod Bank 2.
OP-120 Control Rod Pos Indication Sys Malfunc 3
OP-12E Control Rod Misalignment 2
OP-12F Dropped Control Rod 2
OP-13 Malfunction of Reactor Press Control System 3
OP-14 High Activity in Reactor Coolant 2
I OP-16 Nuclear Instrumentation Malfunctions 3
OP-17 Malfunction of RHR System 2
OP-18A Loss of Charging 1
1 OP-188 Loss of Normal Letdown 1
i OP-19 Malfunction of Reactor Makeup Control 2
OP-20 Excessive Reactor Coolant System Leakage 3
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TITLE REY i
OP-21 Loss of A Coolant Loop RTD 2
OP-22 Emergency Shutdown 1
OP-23 Natural Circulation of Reactor Coolant 3
OP-24 Loss of Containment Integrity 1
OP-25 Tank Ruptures 3
OP-26 Excessive Fe'edwater Flow I
0P-27 Irradiated Fuel Damage 1
OP-28 Startup of an Inactive Reactive Coolant Loop 1
OP-29 Excessive Load Increase 1
OP-30 Inadvertent Load Fuel Assly Improper Pos 1
OP-31 System Under Frequency 1
OP-32 Rod Ejection 1
OP-33 Loss of Instrument Air 1
OP-34 Generator Trip - Full Load Rejection 1
OP-35 Loss of Vital or Non-Vital Instr AC Sys 1
OP-37 Loss of Protection System Channel 1
l OP-38 Anticipated Transient Without Trip (ATWT) 5 i
OP-39 RCP Locked Rotor Accident 1
OP-40 Accidental Depressurization of MS System 1
l OP-41 Hydrogen " Explosion" Inside Containment 1
OP-44 Gaseous Voids in the RCS 2
j R-1 Per Injury (Rad Related) And/0r Overexp 12 i
R-2 Rel of Airborne Radioactive Materials 4
R-3 Re1 of Radioactive Liquids 3
R-4 High Radiation (In Plant) 3 i
R-5 Radioactive Liquid Spill 3
R-6 Radiological Fire 7
i R-7 Offsite Transportation Accidents 4
M-1 Employee Injury of Illness (Nonradiological) 11 M-2 Nonemployee Injury or Illness (Third Party) 10 l
M-3 Chlorine Release 5
i M-4 Earthquake 7
l M-5 Tsunami Warning 5
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M-6 Nonradioloclical Fire 9
i M-7 011 Spill 150 and Clean Up Procedure 6
l M-8 Containment Emergency Personnel Hatch 0
M-9 Hazardous Waste Management Contingency Plan 1
M-10 Fire Protection of Safe Shutdown Equipment 0
G-1 Emergency Classification and Emergency Plan Activation 4
G-2 Establishment of the On-Site Emergency Organization 4
G-2 51 Emergency Organization Call List Forn 69-10297 0
G-3 Notification of Off-Site Organizations 2
G-4 Personnel Accountability and Assembly 3
G-5 Evacuation of Nonessential Site Personnel 1
07/20/84 i
0502d/0005K l
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69-9018 3/84 (200)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPA9TMENT OF NUCLEAR PLANT OPERATIONS DIA8LO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: NEW/ REVISED / RESCINDED 0FFICIAL PROCEDURE INSTRUCTION SHEET
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For Plant Manual Copy No:
Date:
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Responsible Person NEW PROCEDURE
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l Proc No. Rev No.
Vol No.
Section Proc No. Rev No.
Vol No.
Section l
1.
Remove the history sheet (for departmental use as htermined by each dept head).
2.
Insert the attached new procedure into the designated volume.
3.
Enter the procedure title and revision on the Table of Contents.
i 4.
Sign and return this instruction sheet as soon as you have completed above.
i l
REVISED - % io Proc No. Rev No.
Vol No.
Section Proc No. Pev No.
Vol No.
Section I
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1 1.
Remove the history sheet (for departmental use as detemined by each dept head).
2.
Insert the attached revised procedure into the designated volume, 3.
Remove and return the out-of-data procedure and any on-the-spot procedure j
changes associated with the procedure.
4.
Update the revision entry on the Table of Contents.
3 5.
Sign and return this instruction sheet as soon as you have completed above.
i RESCIMOED PROCEDURE i
Proc No. Rev No.
Vol 'No.
Section Proc No. Rev No.*
Voi No.
Section 1
j o
j i
1.
Remove and return the cancelled procedure and any on-the-spot procedure chang s 1
associated with tte procedure.
l 2.
Line out the proceN ro entry on the Table of Contents.
j 3.
Sign and return this instruction sheet once you completed the above.
j REMARKS:
i i
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INSTRUCTIONS COMPLIED WITH:
Date:
Responsible Person 4
RETURN $1GNE0 INSTRUCT!
SHEET,TO:
DE*ARTMENT OF NUCLEAR PLANT OPERATIONS L
DIASLO CANYON POWER PLANT L N (Document Control Clerk)
ATTENT!0N slu.b a
kE IEVERSE SIM PGt INETECTIGS WLtat Pb MSPONSIBLE B0X MSPON51BLE 801 M5M51RE 801 RESPONSIBLE 801 40LDER MOL R PERSON NO PERSON NO PERSON NO PERSON NO j
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1 aCThornberry A3 41 peNeeren N/A 81 WKeyworth F4 121 Q's 88 2
361ffin N/A 42 PPrevence N/A 32 m'bk, M/A 122 3
JOShiffer N/A 43 TJMartin
$3 83 P01sen til 123
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$ 4e sno, 124 DCremins L11 4
lec M9 44 Shift Sec Suprv E9 84 5
Library N/A 45 A04ess N/A 95 WAO' Hare 34 125 OMalone A14 i
6 46 VRFoster 16 06 W Peterson 54 7
SFN 08 47 OAdellace N7 87 IBlalone A10 8
Centrol ihm OS 44 WVidelta 06 38 JNubble K11 9
Aus B149 Cat Brt 08 49 lucienninte C4 W
Emelsensen N/A 10 50 Re1 Shift Suprv OS 90 IS0reke K11 11 Not Shutdemn Pn1 08 51 Cold Shuten Pal OS 91 7,$"/#8'"I N/A
.12 500KV Switchyd 08 52 SvJohnson NB St Clearance Coord OS 13 53 Press Celth Shos All 93 IK Trnt
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.Bestsclon N3 54 P250 Camp h NB M
Idletelt All s/
95 RJTucker All 15 RS$nyder BS 55 se4MbFec/
l 16 NAFer9uson 84 54 h rphy 14 96 JNill 113 17 57
$$'"I N/A 97 setunde N/A 14 Counting Rean 311 54 PPKristensen Ill 98 PSteiner N/A 19 IK Foremen All 59 t$Crockett DO 99 70rtus N/A i
20 Electronics Lab All 60 JA$esten 03 100 LFisher K12 21 Celth shop All 61 0584 N10 101 IE.tou 011 22 Net Instr Shop All 62 JVSeets 53 102 OScoon E4 f
23 3WGiffin A10 63 letrajiasta N/A 103 ELFisher 010 l
24 not Toer All 64 104 OESundquist E3 25 OINiklush C3 65 Isutyen C10 106 EOF N/A l
26 nochenical Frum C11 84 TSC R/A 106 EOF N/A I
27 Electrical Frun C9 67 TSC N/A 107 lancLene 19 IS Cold Mech Shop C11 60
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69-9392 4/84(100)
PACIFIC GAS AND ELECTRIC CCMPANY Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 SKIN AND CLOTHING DECONTAMINATION REPORT RCP G-4 NAME EXPOSURE 10#
DATE/ TIME RWP/SWP'NO.
DECONTAMINATION LOG NO.
Plant location where contamination occured Cause of contamination Skin condition after decontamination Radiation Protection Tecnnician Use drawings below to identify where and what levels of contamination present. Show post decontamination levels.
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CHEM AND RAD. PROTECTION V. Morales
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INSTRUCTIONS:
Complete Appropriate Columns 1.) PROCEDURE PAGE CHANGED ADD PAGE DELETE PAGE NEW PAGE NUMBER l
10 5
1 2.) ATTACHMENTS Attachment Number (Include all pages with dates chanced to date of this OTSC)
- 2 page 10 FORM 69-11510
- w a-w..t-Incoporate use of new survey form.
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oiAsto CANYON POWER PLANT UNIT NCNS) 1 AND 2 NUMBER EP R-1 1
REVISION 12 DATE 2/20/n;cw i
PAGE 7 0F 16 tira' PERSONNELINJURYORILLNESS(RADI0 LOGICALLY RELATED)AND/0ROVEREXPOSURE b) 150 rem to the skin.
c) 375 rem to the extremities.
2)
The patient shows signs of radiation sickness, such as nausea, vomiting, extreme sweating, weakness. diarrhea, i
extreme anxiety incoherence, sensitivity of the nerves l
(tingling or itching sensation).
3)
The patient shows evidence of radiation dermatitis (skindamage). Except for extremely high skin dose f
(greater than 5.000 res) in which case pain occurs promptly and is intense, the symptoms at the time of exposure are a sensation of warmth and itching.
Redness, blistering and other ' effects may not appear for several days.
If the patient requires transportation to the hospital.
c.
during the interval until the ambulance arrives keep the patient comfortable. Survey the individual and perform any decontamination which circumstances require and/or permit.
Do not agoravate any in.iury or unduly alam the patient in performing these operations. Record survey results on the "5 kin and clothing Decontamination" Form (Form 69-9392) anowned i
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In cases of severe contamination, handle as in Step 3.c to save f the extent practical.
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d.
To the extent practical, save all vomit, urine, feces or 1
other samples which may assist the long-tern Site Emergency Radiological Advisor in evaluating the accident. This is particularly important if internal deposition of radioactive i
materials is suspected.
Collect the patient's personnel dosimetry and any materials l
e.
which may)have been activated (if a neutron exposure is suspected such as belt buckles watches..iewelry, prior to sending him to the hospital or releasing him. This will be processed for evaluation.
f.
Subsequent actions will be based upon the results of the evaluation of the external exposure.
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OsAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 4/27/84 i
PAGE 8 0F 16 m '.
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY RELATED)AND/0R,0VEREXPOSURE 5.
Overexposure From Internal Sources The following steps apply to cases where the patient has (or is suspected to have) ingested a significant quantity of radioactive material. If the ingestion was by breathing, this procedure applies any' time that the concentration to which the person has been exposed is greater than or equal to (MPC) x PF, where (MPC) refers to the normal (40 hr.) maximum permissible concentration.
i and PF refers to the protection, factor the patient obtained when 4
a quantitatively fit tested to tne respirator that was worn for the job.
Take any medical action which may(be required as a result of a.
injury or external dose received Steps 3 and 4 above). The treatment of these effects should take precedence over the evaluation of internal exposure.
- b.
Remove and retain for subsequent radiological analysis the patient's clothing and respirator.
c.
Survey the patient thorcughly and record the results on the
" Skin and Clothing Decontamination" Form (Form 69-9392).
d.
Decontaminate individual to as low as practical without causing further injury. If practical, save samples of the decontamination solutions, swabs, and other materials which may be of use in subsequent radiological evaluations.
e.
Count the patient on the whole body counter. The results of this analysis will, in large measure, determine the l
necessity for further medical attention or surveillance.
i f.
Collect and save any urine, feces, or vomit which is passed i
from the patient. The long-term Site Emergency Radiological i
Advisor may request that special urine samples be collected for bioassay.
g.
Subsequent actions will be based upon the results of the evaluation of the internal exposure.
h.
If the patient is sent to the hospital, make arrangements to 4
have all urine, feces or vomit samples retained for radiological analysis.
i I
1 DC0084 8X 1
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ON otAsLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 4/27/84 7gtg'.
PERSONNEL INJURY OR ILLNESS (RADI0 LOGICALLY PAGE 9 0F 16 RELATED) AND/0R OVEREXPOSURE t
REFERENCES 1.
Radiation Control Standard No.1. " Personnel Exposure."
2.
Radiation Control Standard No. 2 " Internal Exposure Controls."
3.
Radiation Control Standard No. 5. " Medical."
4.
Radiation Control Standard No. 8. " Reporting Requirements."
5.
Radiation Control Procedure No. G-3, " Personnel Internal Exposure Control."
6.
Radiation Control Procedure No. G-4, " Personnel Contamination Control."
7.
Radiation Control Procedure No. G-7, "Faafation Surveys."
8.
Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation."
9.
Emergency Procedure G-2, " Establishment of the Onsite Emergency Organization."
- 10. Emergency Procedure G-3, " Notification of Offsite Organizations."
- 11. Emergency Procedure R-4, "High Radiation (In Plant).
- 12. Emergency Procedure RB-5, " Personnel Decontamination."
- 13. Emergency Procedure OR-1, "Offsite Support and Assistance" APPENDICES 1.
Appendix 1. Measures To Be Taken If Medical Care Is Required.
2.
Appendix 2 Factors To Consider In Making A Preliminary Investigation.
3.
Appendix Z, Emergency Procedure Notification Instructions.
o DC0084 9X J
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f0N12 DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE
=0/20/"." $ 20w a
PAGE 10 0F 16 PER!ONNELINJURYORILLNESS(RADI0 LOGICALLY g g" RELATED) AND/OR OVEREXPOSURE ATTACHMENTS 1.
. Fons 69-9221. " Emergency Notification Record."
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- 2.
O m 50 02. "h tt:ti:n S :: ":t: Sr :y nece-d "
3.
Form 69-9392. " Skin and Clothing Decontaminationy"12eport
- 4.
Form 62-4587, " Report of Industrial Injury to Employee."
5.
Fcrm 62-4586, " Employers' Report of Occupational Injury or 1
Illness."
6.
Form 62-6015, " Medical Referral."
7.
Light Duty Program Letter.
8.
Safety. Health and Claims Personnel to Be Contacted for Reporting of Injuries at Diablo Canyon (3/83).
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69-22510.(2000) 1/84 DIABLO CANYON POWER PLA.NT RADIATON AND CONTAMINATION SURVET FORM" a
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/ NUMB'ER EP H-1 3DGrWE Pacific Gas and Electric Company REVISION 12 DATE 5/2/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 5 EMERGENCY PROCEDURE IMPORTANT hj TITLE:
EMPLOYEE INJURY OR ILLNESS (NONRADIOLOGICAL)
TO APPROVED:
Y S 0 i PLANTMANAGEp.)
DATE SCOPE This procedure describes the actions which are to be taken in the event of an illness or injury to an employee which does not involve radioactive contamination or overexposure. Injuries in wnich radiological considerations are involved are discussed separately in the R series of Emergency Procedures. This procedure and changes j
thereto requires PSRC review.
1 APPLICABILITY This procedure is to be followed for incidents involving Nuclear Plant Operations personnel, or other company employees at the plant site at C
the request of the Nuci ar Piant O erations o Partment. In the event P
of an incident involving any other company employee (such as a General Construction Employee), perform only the asterisked (*) steps in this procedure.
IPNEDIATE ACTIONS The employee (s) who are at the scene shall:
- 1.
Render all necessary first aid.
- 2.
Notify the control room (Shift Foreman) as soon as practical.
f0TE: The Shift Foreman may be notified by dialing Ext. 1234 or 779 + 61. Dialing 779 + 61 activates the fire alarm and medical emergency code call. The caller must remain on the phone to enable the Shift Foreman to dial into a conference call.
SUBSEQUENT ACTIONS The Shift Foreman shall direct all subsequent actions until relieved by the long term Site Emergency Coordinator if the emergency warrants it. Such actions should include the following:
DC0152 IXV
otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 M-1 DATE 5/2/84 PAGE 2 0F 5
/
TITLE:
EMPLOYEEINJURYORILLNESS(NONRADIOLOGICAL)
- 1.
Sound emergency signal, code override, or other general warning signal to clear the area if the situation warrants it.
- 2.
Dispatch additional first aid personnel such as the project construction EMT (Extension 1212 or 595-7273) to the scene of the injury or illness if required. Personnel who have not been instructed to provide assistance at the scene should remain on their jobs and stay clear of the affected area.
- 3.
Transport the injured person to a Company panel physician or hospital if the situation warrants it (refer to the attached j
list). If possible, the employee is to be accompanied by a supervisor. The practices which are to be followed if this step is necessary are given in the following section of this procedure.
4.
Secure the names and addresses of all witnesses (both Company and non-Company).
- S.
Perform the notifications required by Appendix Z.
6.
Complete the appropriate accident report (s) and forward to the
(.1 office supervisor for processing.
a.
Form 62-4587, " Report of. Industrial Injury to Employee" in cases where no medical treatment was required other than minor first aid at the plant.
b.
Fom 62-4586, " Employer's Report of Occupational Injury of Illness" in all cases requiring medical treatment (including doctor referral) other than first aid or results in lost time beyond the day of injury.
c.
Form 62-5542, " Report of Automobile Accident" if appropriate.
TRANSPORTATION OF INJURED PERSONNEL 1.
The preferred mode of transportation for injured persons is by Company panel ambulance service. Company or private vehicles should only be used in cases where the delay associated with securing 'an ambulance might result in significant deterioration of the injured person's condition, or when the injury is of a minor nature where use of an ambulance,is not warranted.
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i DC0152 2XV i
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otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER' EP M-1 REVISION 12 j
DATE 5/2/84 PAGE 3 0F 5 TITLE EMPLOYEE INJURY OR ILLNESS (NONRADIOLOGICAL) 2.
When requesting ambulance service (refer to the attached list).
provide the following information to the ambulance service, a.
Name of caller b.
Company affiliation c.
Phone number of caller (where he can be reached) d.
Name of injured or ill person e.
Where the patient is located" f.
Where the patient is to be transported g.
Nature of injury or illness h.
Any other medical information which might be pertinent to transporting the injured person C
Record this information on Form 69-9221 " Emergency Notification Record", or other log.
- 3.
If ambulance or medical personnel are to enter the site, contact the Security Department (3330 or 3363) and have them notify the security force at the Port San Luis entrance. It is necessary to have an escort accompany the ambulance personnel from the Security Building to the patient.
4.
If possible, have a supervisor accompany the injured person to the hospital (or doctor's office). If this is not practical, call a supervisor and have him meet the patient at the hospital I
(or doctor's office). The supervisor should inform the doctor about the Company's light duty program.
5.
If possible, call ahead to the hospital (or doctor) and provide the following information:
a.
Name of caller b.
Company affiliation t
5' l DC0152 3XV L
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-1 REVISION 12 DATE 5/2/84 PAGE 4 0F 5 TITLE:
EMPLOYEEINJURYORILLNESS(NONRADIOLOGICAL) c.
Phone number of caller (where he can be reached) d.
Name of injured or ill person e.
Age of injured or ill person (approximate if not known) f.
Extent of injury, illness or symptoms g.
Medical history (if known) h.
Radiological conditions.1 Record this information on Form 18-9221. " Emergency Notification Record", or other log.
6.
A medical referral, Form 62-6015, shall be completed and sent to the hospital (or doctor) with the injured person alon copy of the Light Duty Program Letter (copy attached)g with a These forms should be taken by the accompanying supervisor, the patient, or the ambulance driver, as appropriate. Do not delay transport of seriously ill or injured persons while obtaining
's, '
these forms.
REFERENCES 1.'
Rule 16, PGandE Accident Prevention Rules.
2.
PGandE Standard Practice 250.
3.
NRC Information Notice 80-06, " Notification of Significant Events."
ATTACHMENTS 1.
Form 62-4587, " Report of Industrial Injury to Employee" 2.
Form 62-4586, " Employer's Report of Occupational Injury or Illness" I If the injury or illness is involved with radiation, see "R" Emergency Procedures. However, the hospital should also be informed when radiation is not involved, because in the absence of such knowledge, they wit rassume that radiation is involved.
4 DC0152 4XV i
.3.
,0 own.O CANYON POWER PLANT UNIT NO(S) 1 AND 2 MB M-1 DATE 5/2/84 PAGE 5 0F 5 TITLE:
EMPLOYEE INJURY OR ILLNESS (NONRADIOLOGICAL) 3.
Form 62-6015. " Medical Referral" 4.
Form 62-4542, " Report of Automobile Accident" 5.
Form 69-9221. " Emergency Notification Record" 6.
Light Duty Program Letter
- 7.. Company Panel of Physicians, Ambulance, and Hospitals serving the innediate area around Diablo Canyon.
8.
Panel of Physicians, Ambulances and Hospitals, Coast Valley Division, SP 251.1-1.
9.
Safety. Health and Claims Personnel to be contacted for Reporting of Injuries at Diablo Canyon.
- 10. Appendix Z, Emergency Procedure Notification Instructions C
i DC0152 SXV j
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- n,ne il PACIFIC GAS AND ELECTRIC COMPANY Reper: of Industrial injury to Employee 1.
Name 8.
Division 2.
Addrums ZIP 3.
Telephone No.
7.
Department 4.
Somal Security No.
- 8.. Dam of Acadent 5.
W%
9.
Time of Accident
- 10. Lacetion of Accident
- 11. Nature of injury
- 12. What were you doing and how did accident occur?
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- 13. Describe First Aid rendered:
- 14. Witnesses m acesdene 1.
2.
3.
15.
Sipatureof Employee
- 18. Dam injury reported:
- 17. Dam 30 days elapses:
18.
- See Over Signature of Supervisor INSTRUCTIONS: This report (items 1 thru 15) should be serferen and sped by me employee person-aW and countersigned by me supervisor it is for all Industrial injuries and is in duolicate. The original is a be retained for Company records; the copy is a be detached after completion and given m the employee. Before sgning in item 18;11 e mperwsor should fill in the dam of the report (ltem 16) and I
compus and netste me dass.10 dagfrom the due the injury wee reported (Item 171.
i i
If the smoloyee later requires treetment by a docer or becomes disablest, Form 82-45m must be prepared and forwarded to me Safety, Hemith and Claens Department /MMEDIATELY accompanied by the enginal of this report i
If the smoloyee is unable to fill out or sign this report, it should be prepared, agned by the supervisor and the employee should be given a copy wiein 5 days as required by law.
If me. injured amoloyee cannot write English, me report may be made according to a verbal statement.
If necessary, the smoloyee may sign by a mark and a witness to the report should sign below the em-picyee's mark.
6 m
iL
l INFOmedATION POR THE ifuURED thePLOYEE Thss nouns aussuolems wnn me CaNiemse Lamar Csee L Gesumed lufusenessem The Caveeny has m essnene esfery prog'am a hee Ns empeyams eweid insury, la me of a were.
rused.wieury rue.sartng medices age, spanned esevesen nas been meno for tne test enusaces swwemms asesimese.The Conveny is very neuen senasmed wem Ms insures eneaeyens, and is somse a emune sne musiend pnieren esseemost euer years of emeerwnes for your genefit. Every.
_r effort usils to eswound in menennaing ine arent ese euronen at your inenserief insury.
The Casessy is esnessey getf innesed for luudisdetal beiurtes a fu gruotsyens spfeage arte east of ased ensur in Wie emucus 'ef scient. All _ -_ ___ _ tunefHs. inusue6ne numemmt wasunent, remissaan seepume. and 88ammty soyments are r.___ -
try em Casessy. of eumamens ario, same emnert yew suserveur, at aammies ammmam Thraup eenanuing efferu. me Caneeny has utS4med me unene of hsgfwy suenfied envasaste sud secaskas ereureus PG&E sysumm. A sonst of easters femslier warm tne venous Cemenny progrwns and genefits. inumaling me lignt euty more pseyam,has aman zz us ersween a pessor servens a the insuses empeeves Yeis se eseems a vuesse mesand, surymol, and hoorest surwimme and susadius sammenmey nusuwus to mere or roeisse you fuern tne g
effects of your segury, siaeuewig vesrong see asus asah tresses as ervennes osed areflams tamba. Ammmennees _ __
arquenas in.
emmenad to womenant win asse to suoname.
IIL Seamamma of Tsummme Plevenumm: Trusesent of inmusstel.sasused evelsymms is esensed my me assetever at tne seseover's amenas witn me emseeves howeig wie essoresnety to ensige g...
_ if segrad. Ca6Honte ben seresiser suussowess une mamanus en we.
Ehssmas inee ry to to wasued her a snvenim er at a fusNity of meir snaams solmin e.
__ _ esegreneessumesumenesyJOeprs enwe es. wowesmeries, er usunum =ey my veur serunnes say==m.p e eemd yos netw.e v. Cas my arte a yew nieury.
w e w=n = sessenus vow oreem semes nt, vos may e m. It is e===iesusand est ve emmen m =sm me say n est nas v
toen provised. tort if you woun a enange esswes. neuffy year -
-. The Cosmusw's
_.__ la tale area le sweisse is es.
est you in messung sie sweest seemesene eye. N yes enest toafusage is enseuervecesg susymeman er famiRey sfter 30 esys.you snust nettfy your -
of me none and meereus of 1ste sevsedan er fuspity you hoe seemeums to sananne wesenent. You sneues ensus mie -
- a to tres anyseman er feuilHy so gesy uses te nettfled of ifne brunesises asuty to report to tne Cenemnr a re.
C (i
eswas any Jessen del 2J et sie t. amer han if ins fasiasty or anymean resuman. you are recuares to een a snesame L.._.. _ _ re.
- m e s~eer,s.f es.sec u te - m e. C.u.esy.
IV. Asument of hmemunusy Pam tf your sumstfy amus enemmes 3231J10'. vens me entesems to 1 sus mentveweiTemoosery Diammility in, usumney of $154.00 per amos, essenenene en wie de fun any efer lasery. If me _/.
- ineury romans in hoorsonamnen er senere seen 21 esys of epismeinty, serments will ammmuner me is fus esy of simusiilty. If your etummHNy rumsfu in toe time for suer tuse vuurt er you lame tune sfsor tese veers. vens usell to pas 4 ansoorary dimmellty at ins reus oursentry in effect. Thas assises i
enfy 13 misertes ese er efter 1-1-75. Pomennent esmanhy is seus et sie tem of SM sur nest.
V.
Effsetese Jumary 1.1975.mo sneasyar snust eruutos e senemistusteen speywn for any esenswee waere sie trasong anymoon sevues tne Canomey inst suo enseeves was to undser a rossen se him umsel aud -
se me time of we.
jury, en a sennment tems.
This ornyun previses sorwicus asen a woestional seuduetten, sunsnesting, feurninsng. Innhselng enese.see tranweg spud sensament nemusury to rummere tree sneesress emodeves to esitumes amoneyment, useien is not emnfhud to._._ _
wem PG4E. The Com-seny meres in _._
_ une me Castfernes Ransedeemnon Susens.
VI. Demon Osammer If your insury runste in essen and yens home a stesNy.
. mense. Wie men of 350A00.00 le tne massenwn tenerft, emmert ' t came svuoswing a mouse ese one er suisse -
-. minor entesen. tne mesamum is 555,000JIO. There is seus a s
setensnisse tuner esassmanse of 51.500JIO. In sumo et sorties _
_ _.. tne assem pensftt win to e asm seios a four tunes tne egneunt spuunasily M as sie assert of gue _
_.-_ foot u ommed MON V18. Purseur Infessusalon If you west fisrmer infomestian en veesr sortinutur amm. In adWesen to sunst your asperw4ser has orovisud.
annust 1pse Wernors Canomammten Cleens Sosteen 44153 731-4211 Emunmen 3171.
Informassen and Asmanenes Off'sers leases la me offinns of me Diveen of inmusstes Aamnesnts.Werners' Consenesten Assess a
Beere we e furmer smures of miformeteen and asnness. The Wormers' Commonastnen Assumes Samre le ins finns arerwr of cemens tg userters _ _ ___
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w v.m.us se vem reene mass, Mme als of me insannmaan enamn'samen me=== es ames and N it in your umummed -.
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l e tres.Dusse of one enessvuoissemomme pavenhme.The erfusehy emma W meessenves une-
- is eswouns wumevuest sweens in Lamar Came Sumeen de00 anent:
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(1) The susne one assum of bikmus ammaevens i
III The esempemi nuesmms hemary a samous W me _-
e Q1 Msuings ese.._
448 The mesmuses ammamane reserums W me emessenes W The possume amamus,summe and esmenn of summuumst:
W If ampuurema,esemesummed z _ mus:
- 17) An emmmen a se ammmer suddial susutsamet duImmuley is a he enemommme end.W pumano,an ammmesof heammuse:
C.
W Ade ammmen a a unmeur tne asemasves anal sueuemumy to esse a sagsgo se sus amuss.
eng ammeg swearneme et om esueef begury.
Ist as ruummumseinurans asweg emus sumuseme mesner usepass rumore a en enuesvar see, i
seemsauw.,ummet useseny to es esensvar usuur:
l al Thee-movereen mem es=usrunswie===
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III The emmanvuure emmehamn rummsire neue er nur e ammie=us:
j CSI Manssuemusen er augury le ineaume ersummausumumes i
let The asumasvavs eenmemen tumusum -.
. mas smusemary:
W The enemmoven's emnetense unangmas a assumousy styvfleet ansages tees i
tumart sams6 auunne a supussemur of suo speammes amarum of sumusumet renssrug.if ury, W ffmW 6 W 7,,s.u.a is,us.,m. m
.su,
- m..m z D3 The esimBWTee rummeumasy fm em ammsunnum evervsualmst.
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,e MhC3Pic GA4 and EL.5CTRIC COhePANY Ernedover's Mooort of Qasmestones Injury or II:nses CCNFIDENTIAL-for Uar av Comentsv Atromovs oivrsease espegnat oeWets om esseenat casustnucTions wur== rum.t u
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Kindly give to bearer, 1
Mr.lMs.
medical attention, and forward a complete detailed resort immedi.
asety to Manager. 5afety. Health and Cairns Dept. 245 Market Street.
San Francisco,94106. Your tills shoeid be leemsaed and all bills and reports rendered in tripsicate.
PACIFIC GA5 AND ELECTRIC COMPANY sy I**=
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- -*--s==.
PLEASE COMPT.ITE AND RETURN TO EMPLOYEE isawsovsa must wave comartma cAmo to asTwan To woes)
Pacific Gas and Bertric Co.:
Dam
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Occupadon Report e Employed 8y l** =
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laiured at E on
,19 C Aseen to fWi work imunamissWy C sneemse wert uses c u m me a e unas C Raumsesseerfinuadem Q namen Aest.
Thus:
C Dimeursum hem womunen sipes
- 40. -
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-l Confidential l For Use by Company Attorneys Only l
@ REPORT OF AUTOMOBILE ACCIDENT OTHER DRIVER Name se cww.s e N
ACCloENT REPORT NUMSER Bath Lic. No.
State Alphe Year Seq. Numtier Ont. Usel insurance Company
@ OTHER VEHICLE OR PROPERTY OWNER Name Addres Phone No Vehicle: Make Type Year Lic. No.
Cokw NAME ADDRESS PHONE No.
nienMiam witness $ITat 1
O O
O PASSENGERS IN OTHER 2.
O O
O VEHICLES.
1 O
O O
WITNESSES.
4-OR INJURED 0
0 0
PER30NS 5.
O O
O 6.
O O
O esaans AcoREss
- PHONE No.
v"as a $I 7'at b
1.
O O O
PASSENG RS 2
O O O
U COMPANY VEMICLE 1
O O O
4.
O O O
0 ATE IME wCA=
'n Other vehicle was O stopped O moving ori et MPH h
Company vehicle was O stopped O moving on et MPH DESCRIPTION
,0F ACCIDENT Complete detaile of how we _ _
.-.-v.
escurreg Describe weather, road and light conditioe-Number of seet belts in Company vehicle Number of seat belts in use et time of accident Indicate which investigatino egency wilt preoare e report-Ocup C shea+# O ce, s s O Nea.
Oome e
DESCRISE DALAGE TO:
Costif known or estianate:
M Other Vehicle (s) or Property 0under $500 V
O Over $500 VEHICLE a ovo, gioco DESCRI8E DAMAGE TO: O Company vaicie O Lemos/Rentei Vehicle OPersonas vehicie Costif known or estimete:
PROPERTY DAMAGE O Undw S100C D Over $1000 I
were onotos tatea of accident scene end osmaae*
O ves O No OOm 36000 g
Company Driver Home Address Company Phone Nem COMPAgy Age Occupation poporting to Local Office et DRIVLA g
Cal. Driver's Lic. No-Osos Emperation Date INFOR AT ON Oswh or G.O. Dept.
District r'----
Vehicte No.
Lic. No.
Lic. No.
Type
((
Odo.- s; Readig Driver's Signatura Dete of this report 19 CountersW Company Phone No Location om eveu see accowest si
, Jgoegoongss,agig me es. isgsojogvnnemias a c.
- i 4
- -. ~. -
- - - -. - - - -. -. - - - ~ ~ - - -
- - - ~ ' - ~ ~ ~ ~ ' "-~' *
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BilSTRUCTIONS All accidents arising out of the operation of Company. owned, leased or remed vehicles, as well as employee owned, leased or rented vehicles used on Company business, must be reported to the Supervisor in charge immediately. All injures to persons or senous demoge to property of others involving above vehicles must be reported to the Safety. Health and Claims Department Field Investigator or,if he is uneveilable, the General Office Safety. Health and Claims Department. Such notification shall be by the fastest means of communication and this report prepared the same day. Answer each question fully. When blank spaces are not sufficient for full statements, answer each on separate sheets and attach hereto.
PREPARE A SKETCH OF ACCIDENT BELOW: Sketch should show-4 POS TION OF VEHICLES. BUILDINGS. STRUCTURES. ETC.
- 2) STREET NAMES. DIRECTIONS OF TRAVEL STOP OR WARNING SIGNS, ETC.
=
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t i -
Page 1 of 2 l
4/84 DEPARTMENT OF NUCLEAR PLANT OPERATIONS i
DIABLO CANYON POWER PLANT Company Panel of Physicians, Ambulances, and Hospi{als Serving the Immediate Area Around Diablo Canyon 2
Ambulance Name Address Phone Remarks San Luis Ambulance 358 Santa Rosa 543-2626 Radiation Exposure Service San Luis Obispo Patients Five Cities Ambulance 135 South Halcyon Rd.
489-4241 Service Arroyo Grande l
South Bay Fire / Ambulance 2315 South Halcyon Rd.
528-1414 Arroyo Grande Bay Ambulance 510 Bonita 772-2626 Morro Bay l
C l
g CENTRAL DISPATCH FOR ALL OF THE AB0VE AMBULANCE SERVICES 543-7911 Hospitals French Hospital 1911 Johnson Avenue 543-5353 Radiation Exposure San Luis Obispo Patients-External Defib. Equip.
- Sterra Vista Hospital 1010 Murray Avenue 543-6550 External (20 minutes to clear for San Luis Obispo Defibrillation helicopter)
Equipped Arroyo Grande Comunity 345 South Halcyon Rd 489-426]
External Hospital and Medical Arroyo Grande Defibrillation Center Equipment I
i o
DC0152 6VIII
i i
j
,Page 2 of 2 1
i l
Physicans l
San Luis Medical Clinic 1235 Osos Street 543-5600 San Luis Obispo
- Richard E. Fleming 1235 Osos Street Industrial Injury
{
i San Luis Obispo Treatment and Eye
[
Injuries I
T. A. Beresky 100 Casa Street Eye Injuries t
l San Luis Obispo -
l
- 0 avid W. Ralston 1941 Johnson Ave.
Industrial Injury Suite 203 and Preemployment San Luis Obispo Physical Exam,s Laurence H. Lotz 1941 Johnson Ave Industrial Injury
[
Suite #T and Preemployment L
San Luis Obispo Physical Exams
(
1.
This list extracted from Standard Practice No. 251.1-1, Panel of Physicians, Ambulances, and Hospitals, Coast Valleys Division, dated 9/29/83.
i 2.
See also EP OR-1 "Offsite Support and Assistance" for Air Ambulance and Medical Support.
'Willing to fly
- Helicopter landing facility available l
i l
OC0152 7VI!!
PACIFIC GAS AND ELECTRIC COMPANY SAFETY, HEALTH, AND CLAIMS DEPARTNENT PANEL OF PHYSICIANS, AMBULANCES, AND HOSPITALS COAST VALLEYS DIVISION SP 251.1-1 Page 2.1 Issued: 9/29/83 t0WN ADDRESS TELEPHONE SERVICE l
l ARROYO GRANDE I
Five Cities Ambulance 135 South Halcyon Road (805)489-4241 Ambul.
Service CENTRAL DISPATCH (805)S43-7911 Ambul.
AA.' Comunity Hospital 345 South Halcyon Road (805)489-4261 Hosp. DEF and Medical Center ATASCADERO
{
Doctors See PASO ROBLES North County Medical 3886 El Camino Real (805)466-1011 Ambul.
Services (Esaergency Medical Technician)
CENTRAL DISPATCH (805)543-7911 Ambul.
Twin Cities Consnunity 1500 Las Tablas, (805)434-2813 Hosp DEF l
Hospital Templeton l
BAYWOOD PARK - LOS OSOS South Bay Fire /Arr6ulance 2315 Bayview Heights (805)S28-1414 Ambul CENTRAL DISPATCH (805)543-7911 Ambul 1
- Industrial Injury Treatment E
- Preemployment Physical Examinations i
EYE
- Eye Injuries l.
- Paramedic Services "0EF"
- Hospital Equipped with External Defibrillators
- Willing to Fly 0
- Helicopter Landing Facility Available RAD
- Radiation Exposure Incidents o
I e
DC0152 8VII
SP 251.1 Page 2.2 Parel of Physicians, Mbulances and Hospitals Issued: 9/29/83 Coast Valleys Division TOWN A00RESS TELEPHONE SERVICE CAMSRIA Cambria htulance 1460 Main Street (805)927-4221 Mbul Service CEhTRAL DISPATCH (805)S43-7911 kbul i
CARMEL Red Cross Ambulance Carmel Fire House, (408)624-3838 kbul 6th & Delores Streets Cc munity Hospital of Carmel & Pacific Grove (408)624-5311 Hosp OEF the Monterey Peninsula Highway l
CARMEL VALLEY l
C. Winter Van Horn Village Medical Center
-E Paulino E. Tocchet 10 Del Fino Place
-E
{
CASTROVILLE Joseph L. Kirch 11272 Merrit Street I-E 3
Bert Clair Eliason 10349 Merrit Street I-E HOLLISTER l-
[
N.L. Currie 390 Seventh Street I-E Martin M. Bress 931 Sunset Drive I-E 1.
Stephens & Poletti 328 Fourth Street (408)637-7474 Ambul i
htulance I
Hazel Hawkins Hospital 911 Sunset Drive (408)637-5711 Hosp OEF KING CITY Duane F. Hyde 210 Canal Street
-E South County kbulance 124 North Second Street (408)385-4841 ktul l
George L. Mee Memorial 300 Canal Street (408)385-5491 Hosp OEF
)
Hospital l
l i
0 DC0152 9VIII
Page 1 of 1 i
PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNITS NOS. I and 2 TITLE: EMPLOYEE INJURY OR ILLNESS (NON-RADIOLOGICAL)
ATTACHMENT 10 EP M-1 APPENDIX Z 1.
When this Emergency Procedure has been implemented for injuries or illnesses occurring within th plant gate, and upon direction from the Shift Foreman, proceed as follows:
- a.
Notify the Plant Manager or his designated alternate.
t
~
Notify the Compensation Claims Representative, Department of Safety b.
Health and Claims, per the attached list of personnel.
- c.
Review the circumstances causing the injury or illness against the criteria for reports to NRC contained in Administrative Procedure C-11, Supplement 1, " Supplement I to Non-Routine Notification and Reporting to the NRC and Other Governmental Agencies". Appendix I.19, " Reporting of Significant Operation Events". If circumstances warrant, designate the event in accordance with the criteria contained in Procedure C-11.
g
- d.
Also notify the following if NRC is notified - Supervising Nuclear Generation Engineer (Personnel and Environmental Safety) or his alternate in the Department of Nuclear Plant Operation:
Mr. W. H. Fujimoto PGandE 222-4004 Plant Extension 3277 i
Home (415) 799-5080 NDTE: If the above General Office person cannot be promptly reached, i
request the Systems Dispatcher to contact alternate personnel.
i 1
e l
V DC0152 161X
,_____-.._.-,_-_,-._..,____,_.._I
/
SP 251.1 Page 2.3
~
Panel of Physicians, M:ulances and Hospitals Issued: 9/29/83 Coast Valleys Division TOWN ADDRESS _
TELEPHONE SERVICE LOMPOC Comnity kbulance 410 East Locust (805)736-7547 kbul Service 736-8550 Lompoc Hospital District 508 East Hickory Avenue (805)735-3351 Hosp OEF 736-1201 LOS 0505 South Bay Fire Bayview Heights (805)S28-1414 kbul Department /Mbulance CENTRAL OISPATCH (805)543-7911 s
i MONTEREY W.A. Carnazzo 464 Pacific Street
-E j
Nello P. Torri 1010 Cass Street I-E Howard Press 172 El Cerado I-E
!l John J. D'Attilia 880 Cass Street Eye t
George S. Campion 1010 Cass Street Eye
! C Eskaton Health Care 576 Hartnell Street (408)375-2621 Hosp DEF Center (24-hour Emergency Service)
Peninsula Corrunity Carmel & Pacific Grove (408)624-5311 Hosp OEF Highway, Cannel MORR0 BAY Bay ktulance 510 Bonita (805)772-2626 Mbul 0
DC0152 10VIII
m SP 251.1 Page 2.4 Panel of Physicians, Mbulances and Hospitals Issued: 9/29/83 Coast Valleys Division TCWN ADDRESS TELEPHONE SERVICE PASO ROBLES
- Stanley J. Kirk 1305 Vine Street Physicians' Exchange Professional kbulance 1035 Vine Street (805)238-2545 ktul Service CENTRAL DISPATCH (805)S43-7911 ktul Twin Cities Hospital 1500 Las Tablas Road (805)434-2813 Hosp OEF Templeton i
SALINAS
/
W.H. Lawler, Jr.
110 John Street E
Howard C. Miles 535 East Remie Lane
-E Glenn H. Smith 230 San Jose Street ye j
E.O. Dong 535 East Romie Lane i
ye I
Robert Avila I'
102 San Miguel Ave.
I-E l
t l
L A-1 ktulance Service 241 East Market Street (408)422-2020 Antul EMERGENCY 911
/
~
i Salinas Valley 450 East Romie Lane (408 757 4 3 Hosp OEF l
Memorial Hospital l
Robert G. Van Horne 236 San Jose Street E
SAN LUIS OBISPO
- Richard E. Fleming 1235 Osos Street 1-E l
l
[
T.A. Beresky 100 Casa Street Eye r
Laurence H. Lotz 1941 Johnson Avenue I-E Suite T j
SLO Medical Clinic 1235 Osos Street (805)S43-5600 l
l San Luis keulance 385 Santa Rosa (805)S43-2526 htul RAD Service CENTRAL DISPATCH (805)S43-7911 ktul
?
French Hospital 1911 Johnson Avenue (805)S43-5353 Hosp DEF RAD r
- Sierra Vista Hospital 1010 Murray Avenue (805)S43-6550 Hosp OEF k
(20 minutes to clear for chopper)
David W. Ralston 1941 Johnson Avenue
[kE0f)S41-1177 I-E Suite 203 OC0152 111X
O Page 2.5 SP 251.1 Panel of Physicians, &bulances and Hospitals Issued: 9/25/33 Coast Valleys Division TOWN A00RESS TELEPHONE SERVICE SANTA BARBARA St. Francis Hospital 601 East Micheltorena (805)962-7661 Hosp OEF (805)956-1531,
SANTA MARIA
/
Brian J. Kiniry 915 E. Stowell. Suite A Jules Bertero 201 West Cook Street
-E
- Harry K. Lienke 217 East Fesler -
-E
- 0cnald E. Reiner 1414-0 South Miller St.
I 0.D. Shepard 1414 South Miller St.
Eye Industrial Medical Group of Sacta Maria Valley Dr. Betty Suits Tibbs 3130 Skyway Drive,'
-E Suite 702 Or. William J. Tibbs 3130 Skyway Drive, I-E Suite 702 Arrulance Service (911)
Actul PM Santa Maria khulance 602 East Cook Street (805)925-9555 ktul Service Police Department Santa Maria (805)925-2631 Arcul (For Emergency Only)
Emergency 911.
Marian Hospital 1400 East Church St.
(805)922-5811 Hcsp DEF Valley Com. unity 505 East Plaza (805)925-0935 Hesp Hospital SOLEDAD Soledad Actulance Soledad (4083678-2611 Mcul Service 911 (County Emergency f
Services) 4 t
OC0152 12VI!!
E
l SP 251.1 Page 2.6 Panel of Phy icians, Ambulances and Hospitals Issued: 9/29/83 Coast Valleys Division TOWN ADDRESS TELEPHONE SERVICE SOLVANG F.A. Pedersen 2030 Viborg Road
-E W.B. Van Valin 2030 Viborg Road I,-E Coast Ambulance 361 Alisal Road (805)688-8911 Ambul Sedvice EMERGENCY 911 i
Santa Ynez Valley 700 Alamo Pintado Rd.
(805)688-6431 Hosp OEF l
Hospital TEMPLETON Peter S. Davis 1400 Las Tablas, I-E Suite 2 Willard Osibin 1400 Las Tablas I-E
- R.A. Greenman 1400 Las Tablas E
CENTRAL DISPATCH (805}543-7911 Ambul Twin Cities Hospital 1500 Las Tablas (805)434-2813 Hosp OEF WATSONVILLE
- E.H. Eiskamp 850 Freedom Boulevard E
P.K. Gilman 850 Freedom Boulevard
-E David E. Bushman 30 Brennan Street
-E Douglas A. Liddicoat 274 Green Valley Road Eye W. Webb Wilson 272 Green Valley Road Eye A-1 Watsonville 1046A Freedom Boulevard (408)724-2455 Ambul Artulance
Watsonville Coccunity Green Valley Road at (4C8)724-4741 Hosp OEF Hospital Holohan Road l
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OC0152 13VIII l
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PAC I F I C' G.A S ANO ILICTP.IC C C M FA2
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3Aa:.: cA acN set /F 7'.ax!
pc. su ss. A.ua seac.- ca:2.m 93r24. (sts) sis.73n WE.:5?M 4
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Daar Dr.
Thank you f5r being one of our panel physicians that treat our employees.
Our primary goal is to provida employees who susnin industMal injurias requiring mecical at antion with prom;::, first-class : ea= ant. Your assistanca in this endaavor is appreciatsd.
. Thers is an area of concarn to us. While the number of employees cat require t eat =:en: by a physician has.rumained suble or in sci.ie casas caclined, ths ac=ner of disamling injuries requiMag time away from wort,
(
i.e., lost time injuMes, has dramatically increased.
Ife believe that some of this tirse away from work might possibly be avoidad if tne availability of light (modified) dug or desk-type wort were more widely known. Some physicians have stated that in some casas the patient will respond more rapidly to treatment if kaot busy in a light-duty capacity.
Productise, lignt-duty assignments art alacs: always availa51e for ac.ployees releuad for work within 2e medical restMetions established by the physician.
It our policy to have an injured employee accomoanied by a supervisor or other recmantative on ce first doctor's visit. Should there be any ques-tien abou: ce availanility or type of ligne duty that can,ba provicad, he I
or sne will be able to answer for us.
cur apoloyees' welfare is our main concarn. Should you have any questions about our program, I will be glad to call on you at your convenienca.
Sincarely.
e R. C. THORN 3ERRY RCT:kge 8
t
.. _. _ _, _,. _ _,,_,.._,________,____,__,._..._.____,___,_j_.
O I
i 69-9221 3/82 (1 W DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT I
EMERGENCY NOTIFICATION RECORD f
EMERGENCY IDENTIFICATION DATE SHEET PERSON CALLED AFFILIATION TIME REACHED BY MESSAGE GIVEN
RESPONSE
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NUMBER EP M-10 9 6 V4 3 Pacific Gas and Electric Company REVISION O DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 6/11/84 PAGE 1 0F 3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE IMPORTANT TITLE:
g FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT TO SAFETY APPROVED.
PLANTMANAGERM DATE SCOPE This procedure provides analyzed corrective actions to take following a fire (s) in any plant area (s) containing safe shutdown equipment.
Fire areas not containing safe shutdown equipment are not addressed by this procedure. Safe shutdown equipment are those defined in Appendix 2 of this procedure. This procedure and changes thereto requires PSRC review.
DISCUSSION j
The equipment required to place the plant in a safe shutdown condition 1
is contained in various fire areas (zones) within the plant. A fire area is defined as that portion of the plant that is separated from other areas by boundary fire barriers (walls, floor, ceiling) with any openings or penetrations protected with~ seals or closures having a fire resistance rating equal to that of the barrier. The barrier rating is comensurate with the free fire hazard in the area. Fire zones are subdivisions of fire areas and are not necessarily bounded by a continuous fire barrier. Should a fire break out in one of the fire areas (zones), safe shutdown and free fire hazard analysis has demonstrated that the safe shutdown of the unit will not be jeopardized. However, the manual operation of certain safety shutdown equipment may be required depending on the location and severity of the fire.
Safe shutdown equipment are defined on the stipulation that a complete loss of off-site power has occurred, and only diesel power is available. Therefore, this procedure may be conservative at various places. If a fire does occur in an area containing safe shutdown equipment but off-site power or in-house (non-vital) power continues to be available, the operator should continue to attempt to operate i
the plant with " normal" equipment, using the instructions provided in this procedure as back-up.
DC0275 II
i i
NUMBER EP M-10
)
DIABLO CAN ON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 6/11/84 PAGE 20F3 7,7tg. FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT There are more fire zones in the plant than is addressed in this
'precedure. The reason why certain fire zones are not included in this procedure is because those zones do not contain safe shtudown circuits in them.
PROCEDURE 1.
If a fire occurs in the plant the following additional procedures should be used immediately:
a.
Non-radiological Fires - Volume 3 in the Plant Manual.
Emergency Procedure M-6 b.
Radiological Fire
- Volume 3 in the Plant Manual, Emergency Procedure R-6 c.
All Fires
- Volume 11 in the Plant Manual, Fire Plan Section d.
All Fires
- Volume 2 in the Plant Manual.
Fire Fighting Tactics, K-2C 2.
The DETECTOR ZONES (listed in the Fire Plan) do not coincide with the FIRE AREA 5 (ZONES) defined in this procadure. Once the location of the fire is known, detemine which area (zone) it is in by referring to Appendix 1 of this proce' ure, d
FETE: Not all fire zones are equipped with fire / smoke detectors.
3.
After identifying the affected fire area (zone), follow the guidelines in Appendix 3 of this procedure to maintain the operability Of the safe shutdown equipment.
4.
In Appendix 3 of this procedure, whenever the instructions call out for manually closing pump breakers for CCW or charging pumps, be aware that there are dedicated wrenches available in the 4KV switchgear rooms that can be used to open the switchgear doors.
The instructions to manually close the pump breaker are posted inside the door.
5.
Whenever manual valving is perfomed en a motor operated valve, the power supply for the valve should be tripped off at the 480 j
volts load center.
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DC0275 2I e
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NUMBER EP M-10 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 6/11/84 PAGE 30F3 TELE:
FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT 6.
The smoke and fire detectors located throughout the plant are not seismic qualified. Therefore, following any earthquake that registers greater than.02g at the plant, it must be assumed that the detectors fail. Within two hours all fire area (zones) must be inspected for possible undetected earthquake induced fires.
REFERENCES 1.
Fire Protection Review, USNRC Docket Nos. 50-275 and 50-323, 2.
Technical Specification 3.3.3.8.
3.
Report on 10 CFR 50 Appendix R Review Unit 1. USNRC Docket No.
50-275, July 15, 1983 4
ATTACHMENTS Specific information concerning safe shutdown equipment affected by fire is included in this procedure as follows:
APPENDIX 1 This section contains an index to allow the operato" to quickly locate the fire zones, and the page number for the corrective instructions corresponding to the fire zones, when a smoke / fire detector alarm is activated in the Control Room.
APPENDIX 2 This section contains a list of the various systems and equipment required for safety shutdown and also lists the redundant equipment available.
APPENDIX 3 This section contains a list of each fire area (zone) that contains safe shutdown equipment and states where the equipment is. It includes
{
guidelines for maintaining the operability of safe shutdown equipment.
Plant Layout Drawings of Fire Area (Zone) locations and Boundaries.
l DC0275 3I l
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w PAGE I APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN CQUIPMENT
~
DET FIRE-PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
1 1
128' ELEV NR AUX RELAY RACKS /
CABLE SPREAD RM.
7-A 32
~
2 128' ELEV UNDER MAIN CONT BD LVB4/
7-A 3
128' ELEV UNDER MAIN CONT BD:!VB2/
7-A
~'
4 128' ELEY UNDER MAIN CONT BD IVB5/
7-A 5
128' ELEV NR ANNUNCIATOR RACKS /-
7-A 6
128' ELEV NR UNDER OPERATORS CONSOLE /"
7-A 7
128' ELEY NR UNDER MAIN CONT BD IVBl/" A,.
~
"~
8 128' ELEY NR UNDER SAFEGUARDS' RACKS / "
7-A f
9 128' ELEV'~NR CONT I & PROT II RACKS / "
7-A 10 128' ELEY NR PORT I!! RACKS /
7-A A
1 11 128' ELEY UNDER RAD MONITOR RACKS /"
7-A 32 12 128' ELEV UNDER PROT I RACKS / LOCAL ALARM LIGHT 7-A a
13 128' ELEV UNDER PROI II. RACKS / "
7-A j
j 14 128' ELEY UNDER PROT III RACKS /"
7-A j
15 128' ELEV UNDER PROT IV RACKS / "
7-A
=
' PANEL NUMBER.
LEGEND:
PNL
=
i DET ZONE DEiECTOR ZONE, NOT SAME AS FIRE ZONE
=
i DET FIRE OR SM0KE DETECTOR NUMBER
=
i FIRE ZONE =
AS DEFINED BY APPENDIX "R",
FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT ENGINEERING REPORT, REV. O, JULY 15, 1983 GO TO THIS PAGE(S) 0F THE PROCEDURE FOR THE CORRECTIVE OPERATOR ACTIONS THAT MAY BE PAGE
=
REQUIRED FOLLOWING A FIRE IN THE ZONE IN QUESTION 4
j N/A NOT APPLICABLE, BECAUSE THERE IS NOT SAFE SHUTDOWN CIRCUITRY / EQUIPMENT IN THIS FIRE ZONE.
=
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PAGE 2
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APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS 3
119' ELEV OVER 480V. MCC 15J/CND POLISHING AREA NOTE I a
A 3
1 119' ELEV. 4KV SUPPLY FAN ROOM 13-E 35 2
119' ELEV. 4KV SUPPLY FAN ROOM 13-E 3
119' ELEY. 4KV SUPPLY FAN ROOM 13-E 4
119' ELEV. OVER EXCITATION SWGR 13-D 5
119' ELEV. OVER 4KV SWGR BUS F 13-A 34 6
119' ELEV. OVER 4KV SWGR BUS G 13-B 7
119' ELEV. OVER 4K'V SWGR BUS H 13-C l
i NOTE 1: NOT ASSIGNED DC0275 SI
4 PAGE 3 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOW'l EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
4 1
104' ELEY. UNDER 4KV SWGR BUS F/ CABLE SPREAD ROOM 12-A 34 2
104' ELEV. UNDER 4KV SWGR BUS G/
12-8 3
104' ELEV. UNDER 4KV SWGR BUS H/
12-C 1
1 A
5 1
85' ELEY. OVER 480V MCC llD & IIE 10 33 2
85' ELEY. OVER 4 & 12 KV RELAY BD 10 4
3 85' ELEV. OVER 4KV SWGR BUS E 10 4
85' ELEV. OVER 4KV SWGR BUS E 10 j
5 85' ELEV. OVER 4KV SWGR BUS D 10 i
6 85' ELEY. OVER 12KV SWGR BUS E 10 l
7 85' ELEV. OVER 12KV SHGR BUS D 10 8
85' ELEV. OVER 12KV START-UP SWGR 10 i
l, A
6 1
75' ELEV. UNDER 4 & 12KV RELAY 8D/ CABLE SPREAD ROOM 10 33 2
75' ELEV. UNDER 4KV SWGR BUS E/
10 3
75' ELEY. UNDER 12KV SWGR BUS D/
10 f.
4 75' ELEV. UNDER 12KV START-UP SWGR/ "
10 DC0275 6I c
PAGE 4 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
7 1
100' ELEV. CONTM'T PENETRATION AREA / ELECTRIC 3-BB 12 PENETRATION AREA ABOVE CABLE TRAY 2
100' ELEV. CONTM'T PENETRATION AREA / ELECTRIC 3-BB PENETRATION AREA AB0VE CABLE TRAY 3
100' ELEV. CONTM'T PENETRATION AREA / ELECTRIC 3-BB PENETRATION AREA ABOVE CABLE TRAY 4
100' ELEV. CONTM'T PENETRATION AREA / ELECTRIC 3-BB PENETRATION AREA ABOVE CABLE TRAY 5
100' ELEY. CONTM'T FENETRATION AREA / ELECTRIC 3-BB PENETRATION AREA AB0VE CABLE TRAY 6
85' ELEV. POST-ACCIDENT SAMPLE AREA 3-BB 7
85' ELEV. POST-ACCIDENT SAMPLE AREA 3-BB 8
95' ELEV. HVAC RM OVERHEAD / POST ACCIDENT SAMPLING AREA 14-A 36 9
95' ELEV. HVAC RM FLTRS/ CHARCOAL FILTER TEMP SENSOR 14-A 10 95' ELEY. HVAC RM FLTRS/CHARC0AL FILTER TEMP SENSOR 14-A
^
11 95' ELEV. HVAC RM FLTRS/CHARC0AL FILTER TEMP SENSOR 14-A 12 95' ELEV. HVAC RM FLTRS/CHARC0AL FITLER TEMP SEONSOR 14-A t
DC0275 71
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PAGE 5 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWir EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
8 1
115' ELEV. CONTM'T PENETRATION AREA /ABOVE CABLE TRAY 3-BB 12 2
115' ELEV. CONTM'T PENETRATION AREA /A80VE CA8LE TRAY 3-BB 3
115' ELEY. CONTM'T PENETRATION AREA /A80VE CABLE TRAY 3-BB 4
115' ELEY. CONTM'T PENETRATION AREA /ABOVE CABLE TRAY 3-BB A
9 1
115' ELEY. COMPUTER INVERTER 6-A-5 31 2
115' ELEY. 8ATTERY CHARGER 11 ROOM 6-A-1 28 3
115' ELEV. BATTERY CHARGER 12 ROOM 6-A-2 4
115' ELEY. BATTERY CHARGER 13 ROOM 6-A-3 5
115' ELEY. R00 CONTROL CABLE TRAYS 6-A-4 30 6
115' ELEY. R0D DRIVE MG SET 1-1 6-A-4 7
115' ELEV. ROD CONT. CABINETS 6-A-4 8
115' ELEY. ROD DRIVE MG SET 1-2 6-A-4 9
115' ELEY. ROD CONT. CA8INETS 6-A-4 10+18 (NUMBER 10 THRU 18 SHOWN DN UNIT 2 SMOKE DETECTOR LOCATIONS TABLE)
DC0275 81
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PAGE 6 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
10 1
100' ELEV. HOT SHUTDOWN PANEL 5-A-4 27 2
100' ELEV. 480V BUS 1F ROOM 5-A-1 26 3
100' ELEV. 480V BUS 1G ROOM 5-A-2 4
100' ELEY. 480V BUS 1H ROOM 5-A-3 5
100' ELEV. UNDER PART LENGTH ROC C0NT. CAB.
5-A-4 27 6
100' ELEV. UNDER 480V. L. C. 130 5-A-4 7
100' ELEV. UNDER 480V. L. C. 13E 5-A-4 8
100' ELEV. UNDER R00 DRIVE PROGRAP9tER 5-A-4 9
100' ELEV. UNDER 480V. MCC 12J 5-A-4 10 100' ELEV. UNDER 480V. MCC 121 5-A-4 11 100' ELEV. HOT SHUTDOWN PANEL 5-A-4 12 100' ELEV. HOT SHUTDOWN PANEL 5-A-4 13+20 SHOWN ON UNIT 2 SM0KE DETECTOR LOCATIONS TABLE A
11 1
73' ELEV. 480 V MCC 12M AND 12N 3-F 6
2 73' ELEV. 480 V MCC 1DI AND 12N 3-F 3
SHOWN ON UNIT 2 SMOKE DET LOCATIONS 4
SHOWN ON UNIT 2 SMOKE DET LOCATIONS DC0275 91 M-w
PAGE 7 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN FQllIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
12 1
INSIDE CONTM'T NR COL 7 BET INST TRAYS 1-A 1
2 INSIDE CONTM'T BET SG 14 & RCP 14 1-8 3
3 INSIDE CONTM'T BET SG 13 & RCP 13 1-8 3
4 INSIDE CONTM'T BRG 64* ELEY. 150 1-C 5
FLAME TYPE DETECTOR 5
INSIDE CONTM'T OVERLOAD CNTR 13J 1-A 1
6 INSIDE CONTM'T BET SG 12 & RCP 12 1-8 3
7 INSIDE CONTM'T BET SG 11 & RCP 11 1-8 3
8 INSIDE CONTM'T NR COL 12 & TRAY EJ8 1-A 1
9 INSIDE CONTM'T NR COL 10 & TRAY PJ8A 1-A 1
10 INSIDE CONTM'T BRG 265* ELEY. 150' 1-C 5
FLAME TYPE DETECTOR 11 INSIDE CONTM'T NR LOAD CNTR 131 1-A 1
12+14 INSIDE CONTM'T BELOW 140' PENETRATION AREA 1-A 1
FLAME TYPE DETECTOR 15+22 INSIDC CONTM'T BELOW 117' ANNULUS AREA 1-A 1
23+29 INSIDE CONTM'T BELOW 117' ANNULUS AREA 1-A 1
i A
13 1
155' EL CONTROL RM VENT INLET DUCT 8-8-3 N/A A
14 1
155' EL CONTROL RM VENT DUTLET DUCT 8-8-3 N/A DC0275 10I 1
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PAGE 8 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS A
15 1
INTAKE STRUCTURE BETWEEN 480V MCC 14D & 14E 30-B N/A 2
INTAKE STRUCTURE OUTSIDE U-1 ASW PUMP VAULTS 3-A-5 38 4
B 1
1 64' ELEY. WSTE GAS COMP 01 ROOM 3-C 6
2 64' ELEV. WSTE GAS COMP 11 ROOM 3-C j
3 64' ELEV. CABLE TRAYS NORTH WALL / AREA H 3-C
]
4 64' ELEV. CABLE TRAYS NORTH WALL / AREA H 3-C J
5 64' ELEV. CABLE TRAYS NORTH WALL / AREA H 3-C 6'
64' ELEV. RHR PP 1-1 ROOM 3-8-1 5
7 64' ELEY. RHR PP 1-2 ROOM / AREA K 3-B-2 8
64' ELEV. CABLE TRAYS NORTH WALL / AREA K 3-C 6
9 64' ELEV. CABLE TRAYS NORTH WALL / AREA K 3-C 10 64' ELEV. DRAIN PPS i
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DC0275 111
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PAGE 9 APPENDIX 1 - USER'S GUIDE j
FIRE PROTECTION OF SAFE SHUTDOWff FOUIPMENT DET FIRE i
PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS l
8 2
1 73' ELEY. ABOVE CORRIDOR DUCTS / AREA H 3-C 6
I 2
73' ELEV. ABOVE CORRIDOR DUCTS / AREA H 3-C 1
3 73' ELEY. A80VE CORRIDOR DUCTS / AREA H 3-C 4
73' ELEY. ABOVE CORRIDOR DUCTS / AREA K 3-C 5
73' ELEV. A80VE CORRIDOR DUCTS / AREA K 3-C 6
73' ELEV. ABOVE CC4MIDOR DUCTS / AREA K 3-C'
{
7 73' ELEY. A80VE CORRIDOR DUCTS / AREA K 3-C
]
8 73' ELEV. A80VE CONTM'T SPRAY PP 1-2 ROOM 3-F l
9 73' ELEV. CONTM'T SPRAY PP 1-2 ROOM 3-F l'
10 73' ELEV. CHG PP 1-3 ROOM 3-H-2 7
l 11 73' ELEV. CHG PP 1-2 ROOM 3-H-1 i
12 73' ELEV. CHG RHR HX 1-2 ROOM 3-8-2 5
i 13 73' ELEY. CHG RHR HX 1-1 ROOM 3-B-1 i
14 73' ELEV. CHG PP 1-1 ROOM 3-H-1 7
15 73' ELEV. CCW PP 1-3 ROOM 3-J-3 9
16 73' ELEV. CCW PP 1-2 ROOM 3-J-2 8
17 73' ELEV. CCW PP 1-1 ROOM 3-J-1 7
DC0275 12I
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PAGE 10 APPEN0!X 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT i
DET FIRE
{
PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REHARKS 8
3 1
85' ELEV. SI PP l-1 RGON 3-M N/A 2
85' ELEV. SI PP 1-2 ROOM 3-M N/A 3
85' ELEV. 8A EVAP PKG 1-1 ROOM 3-L 9
B 4
1 100' ELEV. HOT SHUTDOWN PANEL 5-A-4 27 2
100' ELEV. HOT SHUTDOWN PANEL 5-A-4 3
85' ELEV. CHEMICAL LAB 4-A 21 4
85' ELEY. CHEMICAL LA8 4-A 5
85' ELEV. CHEMICAL LA8 4-A 6
85' ELEV. CCW HX ROOM 14-E 36 7
5 1
100' ELEV. AFW PPs 1-2 & 1-3 3-Q-2 10 i
2 100' ELEY. SPENT FUEL PPS 3-0 N/A l
3 100' ELEY. AFW PP l-1 3-Q-1 10 1
4 100' ELEV. A80VE CABLE TRAYS 3-X 11 5
100' ELEY. BA XFR PPS/ AREA K 3-X 11 i
I
_ DC0275 131
PAGE 11 APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWI ft]'l!PMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS B
6 1
115' ELEV. FIRE PPs ROOM 3-M N/A B
7 1+9 115' ELEV. FILTER BANK ROOMS 3-P-4 N/A AIR SHIELD TYPE 10+14 115' ELEY. FILTER BANK ROOMS 3-P-4 N/A FLAME DET TYPE B
8 1+9 115' ELEY. FILTER BANK ROOMS 3-P-4 N/A AIR SHIELD TYPE 10+13 115' ELEV. FILTER BANK ROOMS 3-P-4 N/A FLAME DET TYPE-14 115' ELEY. EXH FAN 1 ROOM 3-P-4 N/A 15 100' ELEV./ AREA L 3-P-1 N/A 16 85' ELEY. (FUEL HAND) SUPPLY FAN ROOM 3-P-1 N/A B
9 1
125' ELEY. FUEL STORAGE-3-R N/A B
10 1
140' ELEY. SPENT FUEL STORAGE 3-R N/A FLAME DET TYPE 2
140' ELEY. NEW FUEL STORAGE 3-R N/A FLAME DET TYPE 3
140' ELEV. HOT SHOP AREA 3-S N/A B
11 1+8 140' ELEV. NORTH FILTER ROOM & EXH FAN E-5 ROOM 3-P-7 N/A 9+12 140' ELEY. FAN E-5 ROOH 3-P-7 N/A DC0275 14I
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PAGE 12 l
APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET PNL ZONE DET LOCATION /DESCRIDTIDN FIRE ZONE PAGE REMARKS B
12 1+8 140' ELEV. SOUTH FILTER ROOM 3-P-8 N/A AIR SHIELD TYPE 9+12
~140' ELEV. FAN E-6 ROOM 3-P-8 N/A FLAME DET TYPE 8
13 1+13 140' ELEV. MN CONTROL BOARDS 8-C 32 INDICATING LIGHTS 14+16 140' ELEV. CONTROL CONSOLE 8-C 32 INDICATING LIGHTS 8
14 1
140' ELEV. COMPUTER ROOM 8-A N/A i
2 140' ELEV. SSPS ROOM 8-G 32 3
140' ELEV. REC & STORAGE ROOM 8-E N/A 4
140' ELEV. SFM 0FFICE 8-E N/A i
l 8
15 1
140' ELEV. 500 KV CONT BOARD 8-C 32 INDICATING LIGHTS l
2+5 140' ELEY. NIS RACKS 8-C INDICATING LIGHTS 6
140' ELEV. INCORE INST RACKS 8-C INDICATING LIGHTS 7
140' ELEY. G.F. FUEL DET RACK 8-C INDICATING LIGHTS i
8+12 140' ELEV. RAD MONITOR RACKS 8-C INDICATING LIGHTS 8
16 1+2 140' ELEY. 5-31 & 32 FAN ROOM 8-8-1 N/A 3+5 155' ELEV. CONTROL ROOM VENT ROOM 8-8-3 N/A i
l j
DC0275 ISI i
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APPENDIX 1 - USER'S GUIDE FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT DET FIRE PNL ZONE DET LOCATION / DESCRIPTION ZONE PAGE REMARKS 1
D 1
1 INSIDE CONTM'T BET SG 11 & RCP 11 1-B 3
2 1
INSIDE CONTM'T BET SG 12 & RCP 12 1-B 1
3 1
INSIDE CONTM'T BET SG 13 & RCP 13 1-B 4
1 INSIDE CONTM'T BET SG 14 & RCP 14 1-B 4
i e
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Page 1 of 7 APPENDIX 2 DIABLO CANYON UNIT 1 EQUIPMENT REQUIRED FOR SAFE SHUTDOWN The following list represents the minimum equipment required to bring the plant to a cold shutdown as defined by 10CFR50, Appendix R Section III.G.I.a. and b.
SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/OR COMPONENTS 1.
Emergency Power Supply a.
Diesel generators,1-1,1-2, 2 of 3 required 1-3 j
b.
Diesel fuel oil transfer pumps, 1 of 2 pumps required 0-1, 0-2 c.
Day tank level control valves 1 of 2 LCV's per day tank required LCV-85, LCV-88 LCV-86, LCV-89 LCV-87, LCV-90 d.
125V de batteries 2 of 3 required
- e. ' Battery chargers 2 "of 5 required f.
Inverters 2 of 4 required g.
4KV power supplies to 480 volt 2 of 3 required load centers and load center transfor1ners h.
125V de supplies to 4KV 2 of 3 required switchgear 1.
125V power supplies to main 2 of 3 required switchgear board J.
Instrument ac power channels 2 of 4 channels required a
DC0275 17I
Page 2 of 7 APPENDIX 2 (CONTINUED) i SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/OR COMPONENTS 2.
Auxiliary Feedwater System Auxiliary feedwater (AFW) pumps 1 of 3 pumps required a.
(turbine-driven AFW pump 1-1 and motor-driven AFW pumps 1-2 and 1-3) b.
Associated steam supply valves Applicable only to AFW pump 1-1 for AFW pump 1-1:
FCV-95, FCV-152, FCV-15 Required for AFW pump 1-1 FCV-37. FCV-38 1 of 2 valves required for AFW pump 1-1 0
c.
Associated level control valves:
Pump 1-1: LCV-107 LCV-108 1 of 2 valves required for Pump 1-1 Pump 1-2: LCV-110, LCV-111 1 of 2 valves required for Pump 1-2 Pump 1-3: LCV-113. LCV-115 1 of 2 valves required for Pump 1-3 d.
Water supply and associated valves:
- 1) Condensate storage tank, or No valves required
- 2) Fire water storage tank I of 2 valves required for fire water FCV-436, FCV-437 storage tank. Can be manually operated if required.
3.
Residual Heat Removal System
- a.
Residual Heat Removal (RHR) 1 of 2 pumps required i
pumps 1-1 and 1-2 b.
RHR heat exchangers,1-1 and 1 of 2 Hx required 1-2 c.
RHR valves:
HCV-637. HCV-638 (RHR Flowpath)
I of 2 valves required 8809-A, 8809-8 (RHR Flowpath) 1 of 2 valves required 8700A,87008(RHRSuction) 1 of 2 valves required 8716A 87168 (RHR Flowpath) 1 of 2 valves required
- Components of RHR system are required for COLD SHUTDOWN I
DC0275 181 6
Page 3 of 7 APPENDIX 2 (CONTINUED)
SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/0R COMPONENTS j
d.
RHR heat sink:
4 Component Cooling Water (CCW)
See Item 5 System Auxiliary Saltwater (ASW)
See Item 6 System e.
RHR valves 8701 and 8702 (hot 1 of 2 required to maintain reactor leg RHR suction) coolant pressure boundary during HOT SHUTDOWN. Can be manually opened for COLD SHUTDOWN. Valve power circuits are normally racked out at the motor control center.
4.
Charging and Boration a.
Centrifugal charging pumps 1-1, 1 of 3 pumps required 1-2 reciprocating pump 1-3 (used as backup to 2 centrifugal pumps) b.
Charging pump cooling:
CCW system See Item 5 ASW system See Item 6 c.
Centrifugal charging pump 1-1 Only utilized to start charging and 1-2 auxiliary lube oil pumps.
pumps. Can be bypassed.
d.
Charging and boration flow path
- 1) Using boric acid tanks:
1 Boric acid tanks 1 of 2 tanks requitad Boric acid transfer pumps 1 of 2 pumps required Boric acid filter Only flow path required Valve 8104 Required for boric acid tank flowpath Charging pumps 1 of 3 pumps required.
Valve FCV-128 Required for centrifugal charging pumps. Two manual bypass flowpaths.
DC0275 19I
l Page 4 of 7 I
APPENDIX 2 (CONTINUED)
SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/0R COMPONENTS l
and a) Charging through No additional components required reactor coolant pump seal via RCP seal injection b) Charging through All of these valves required for this regenerative HX and
. flow path valves HCV-142, 8108, 8107 and:
(1) Valve 8145 and 1 of.2 valves required for 8148, charging to pressurizer auxiliary spray auxiliary pressurizer j
- spray, or (2) Valve 8146, Valve required charging to loop 3 cold leg
- or (3) Valve 8147 Valve required charging to loop 4 cold leg or 2) Using boron injection tanks:
Refueling water storage Required for this flowpath tank Valves 8805A, 88058 1 of 2 valves required Charging Pumps 1 of 3 valves required Valve FCV-128 Required for reciprocating charging pump Valves 8803A, 88038 1 of 2 valves required Boron Injection Tank (BIT)
Required Valves 8801A, 88018 1 of 2 valves required 5.
Component Cooling Water System s.
CCW pumps 1-1, 1-2 and 1-3 1 of 3 pumps required b.
CCW heat exchanger 1-1, 1-2 1 of 2 Hx required i
i DC0275 20I i
I ii i
- -,, ~ - -. -. - -. -,, - - - -
Page 5 of 7
\\
APPENDIX 2 (CONTINUED)
SYSTEM AND A'TIVE COMPONENTS REDUNDANCY AND/OR COMPONENTS c.
CCW Valve::
Header) (C;W Misc. Service Required for reciprocating charging FCV-355 pump 1-3 cooling. Can be opened manually if required.
FCV-430, FCV-431 service headers) (CCW vital1 of 2 valves required FCV-364 FCV-365 (CCW to RHR 1 of 2 valves required for RHR system Hx).
cooling. Valves required for COLD SHUTDOWN. Manual operation assumed in event of fai'9re of remote
- control, i
d.
CCW pump 1-1, 1-2, 1-3 Only required to start CCW pump auxiliary lube oil pumps e.
CCW heat sink:
ASW system See Item 6 6.
Auxiliary Saltwater System a.
Auxiliary saltwater (ASW) 1 of 2 pumps required pump, 1-1, 1-2 b.
ASW valves:
FCV-602, FCV-603 (ASW to CCW 1 of 2 valves required Hx) 7.
Main Steam System a.
10% steam relief valves:
1 of 4 valves required PCV-19, PCV-20, PCV-21, PCV-22 Backup to 10% steam relief valves i
provided by main steam code safety valves b.
Steam generator blowdown Required to close to maintain water isolation valves:
inventory for safe shutdown FCV-760. FCV-761,
.FCV-762. FCV-763 DC0275 211 l
.w
l l
Page 6 of 7 APPENDIX 2 (CONTINUED)
SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/0R COMPONENTS 8.
Instrumentation a.
Steam generator level I steam generator required for cooldown SG 1-1: LT-516, LT-517, LT-518, LT-519 SG 1-2: LT-526, LT-527 LT-528, LT-529 SG 1-3: LT-536, LT-537, LT-538, LT-539 SG 1-4: LT-546, LT-547 LT-548. LT-549 b.
Steam generator pressure:
j I steam generator required for cooldown Loop 1: PT-514. PT-515, PT-516 1 of 3 PT's required for that loop Loop 2: PT-524, PT-525, PT-526 t
Loop 3: PT-534 PT-535, PT-536 Loop 4: PT-544, PT-545, PT-546 c.
Reactor coolant system 1 of 2 required per loop 4
temperature:
1 loop required for cooldown 1
Loop 1: TE-413A, TE-413B Loop 2: TE-423A, TE-4238 Loop 3: TE-433A, TE-4338 Loop 4: TE.443A, TE-4438 d.
Reactor coolant system or 1 of 3 wide range pts required pressurizer system:
j PT-403, PT-405, PT-406, Wide range PT-455, PT-456, PT-457 Narrow range PT-474 e.
Pressurizer Level 1 of 4 required LT-459 LT-460, LT-461, LT-406 f.
Source range flux monitors 1 of 2 required NE-31 NE-32 4
l l
1 I
t DC0275 221 s
. _ _,. _ _ _.. _ ~. - _
. ~
Page 7 of 7 e.
APPENDIX 2 (CONTINUED)
I SYSTEM AND ACTIVE COMPONENTS REDUNDANCY AND/0R COMPONENTS 9.
Ventilation for Safe Shutdown Equipment a.
- 480 switchgear room and inverter room supply and exhaust fans 5-43, 5-44 1 of 2 required E-43. E-44
.1 of 2 required Dampers:
H043. HD44 1 of 2 required b.
- 4.16KV switchgear room supply 2 of 3 required
~
j fans S-67, S-68, S-69 c.
ASW pump room exhaust fans 1 of 2 required E-101 E-103
- 10. Reactor Coolant System a.
Pressurizer power operated Required to prevent LOCA due to stuck relief valves PCV-455C, 474, open valve 456 and block valves 8000A, B and C.
- Portable fans are available in the event these fans are unavailable due to a fire.
DC0275 231 i
}L
'Ime.
- Appendix 3 Page 1 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment l
AFFECTED EalIFMNT ALTElWATIVE EDUlFMNUDFERATOR ACTIONS 1
1.0 Fire Area 1 (Fire Zone 1-A)
Containment Annulus Area Elevation 91' l
1.A)
Residual Heat Removal System
- 1) MOV 8701
- 1) Verify MOV 8701 and 8702 breakers are racked out to MOV 8702 prevent inadvertant opening. Idhen needed for cooldown, manually (handle) open valves, or open from Control Room.
[The pressure and temperature interlock on these valves may need to be jumpered in order to open valve from j
Control Room.]
1.B)
Charging and Boration
- 1) 8146 Normal Charging
- 1) Charge and borate via 8147 Alternate Charging a)~ RCP seals b) BIT bypass i
c) BIT j
- 2) 8145 PZR auxiliary spray
- 2) Continue to use PZR normal spray from loop 1 or loop 2 f f i
8148 PZR auxiliary spray bypass offsite-power is available. If not, use PZR PORV's.
1.C)
Steam Generator 810wdown Inside Containment l
Valves
- 1) FCV-760 S.G. #1
- 1) If these valves spuriously open due to hot short.
FCV-761 S.G. #2 manually close their corresponding outside containment i
FCV-762 S.G. #3 isolation valves, which are FCV 151, 154, 157 and 160 and FCV-763 S.G. #4 FCV 250, 248, 246 and 244.
[ ] Statement enclosed is not part of Appendix R review.
1 DC0275 241
w.'
1 Appendix 3 Page 2 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment Atttutu E00lFENT ALTERNATIVE EOUlFPENT/0FERATOR ACTIONS l
1.D)
PZR Level Transmitters
- 1) LT 459
- 1) If all three level indications are lost. use LT 406 at LT 460 the dedicated shutdown panel. LT 406 is cold calibrated, LT 461 therefore adjust for temperature errors accordingly.
4 l
1.E)
Steam Generator Level Transmitters S.G. #1 S.G. #2 S.G. #3 S.G. #4 Fire Protection Review indicated that at least 2 out of 4 level transmitters should still be available.
LT 516 LT 526 LT 536 LT 546 l
LT 517 LT 527 LT 537 LT 547 LT 518 LT 528 LT 538 LT 548 LT 519 LT 529 LT 539 LT 549 1.F)
RCS Temperature Elements Hot Leg Cold Leg Loop 1 and 2 temperature elements or Loop 3 and 4 temperature may be damaged by fire, but not all four Loop 1 TE 413A TE 4138 loops. Use TE's from the two loops still available, i
RCS Wide Range Pressure Transmitters i
PT 403 - loop 4 hot leg PT 406 may have been fire damaged. If so. use PT 403 and j
PT 406* - loop 4 hot leg 405 indications in the Control Room.
PT 405 - loop 3 hot leg
- At dedicated shutdown panel i
l
. DC0275 251 i
hhe*
Appendix 3 Page 3 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment g
AFFECTED EQJIFENT ALTERNATIVE EQUlFENT/0FERATOR ACTIONS 1.H)
Pressurizer PORV's and block valves PORV 474, 8000A Fire Protection analysis of the circuits for these valves PORY 455C, 80008 indicated at least one PORY will be available following a PORY 456, 8000C postulated fire in this area. The worst that could happen is the PORV's will fall as is, closed.
1.1)
Source Range Neutron Flux Monitor NE - 31 One source, range should still be available.
NE - 32
+
I
\\
2.0 Fire Area 1 (Fire Zone 1-8)
Reactor Coolant Pump Area, Elevation 91' 2.A)
Stean Generator Slowdown Inside Containment Isolation Valves FCV 760 - S.G. #1 If fire damage cause valve (s) to open spuriously, close their FCV 761 - S.G. #2 corresponding outside containment isolation valves, which are FCV 762 - S.G. #3 FCV 151,154,157 and 160 and FCV 250, 248, 246 and 244.
- FCY 763 - S.G. f4 2.8)
Pressurizer Level Transmitters LT 459 Not affected by fire in this zone.
LT 460 LT 461 LT 406 DC0275 26I
tune.
- Appendix 3 Page 4 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EalIFENT ALTERNATIVE EQUIPENT/0ERATOR ACTIONS 2.C)
RCS Temperature Elements Loop 1 413A (hot leg) 4138 (cold leg)
Either loops 1 and 2 or loops 3 and 4 should still be Loop 2 423A 4238 available.
Loop 3 433A 4338 Loop 4 443A 443B 2.0) Pressurizer Pressure Channels PT456(N.R.)l PT455(N.R.
l Not affected by fire in this area.
l i
PT 457 N.R.
2.E)
Pressurizer PORV's and Block Valves PORY 474 8000A Fire Protection analysis of the circuits for these valves PORV 455C. 80008 indicate at least one PORV, either 474 or 456, will be j
PORY 456, 8000C available following a postulated fire in this area. The worst that could happen is that the PORV's fail as is, closed.
2.F)
Source Range Neutron Flux Monitors NE 31 One source range should still be available.
NE 32 1
i e
. DC0275 27I
i he i
Appendix 3 Page 5 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment AFFECTED EWIROIT ALTENTIVE EQUIR0fT/0FERATOR ACTIONS 3.0 Fire Area 1 (Fire Zone I-C).
Centrol Rod Drive Area, Containment Building, 100' Elevation i
l 3.A)
Pressurizer PORV's and Block Valves i
)
PORY 474, 80004 Fire Protection analysis of the circuits for these valves i
PORV 455C 80008 indicated at least one PORV, either 474 or 456 will be
}
PORW 456, 8000C available following a postulated fire in this area. The j
)
worst that could happen is that the PORV's fall as is, closed.
]
3.8)
Source Range Neutron Flux Monitors One source range should still be available.
l NE-31 NE-32 I
t 4.0 Fire Area 3-8-1 RHR Pump 1-1 and Heat Exchanger Room. Elevation 58 thru 113 RHR Pump 1-1 If RHR Pp 1-1 is fire damaged, use RHR Pp 1-2 I
i l
5.0 Fire Area 3-B-2 i
RHR Pump 1-2 and Heat Exchanger Room. Elevation 58 thru 113 i
RHR Pump 1-2 If RHR Pp 1-2 is fire damaged, use RHR p 1-1 p
)
I 1
)
{
DC0275 28I
}
[
i.
j tems..
3 i
Appendix 3 Page 6 of 41 l
EP M-10, Fire Protection of Safe Shutdown Equipment 4
I AFFECD EDJIReff ALTEINLTIVE EQUIRefT/0FERATOR ACTIONS j
6.0 Fire Area AB-1 (Fire Zone 3-B-3) l BIT Room. Elevation 62 thru 75
)
i 8803A BIT inlet valves If both of these valves are fire damaged, borate via normal 88038 CVCS boration path.
I l
7.0 Fire Area AB-1 (Fire Zone 3-C) l Drain Receiving Tanks and Gas Decay Tanks Area. Aux Bldg. 75' Elevation l
i 7 A)
Diesel Fuel Transfer Pump 0-1 power If damaged by fire, use Diesel Fuel Oil Transfer Pump 0-2.
i t
{
7.8)
Aux Feedwater Pump 1-2 Control If damaged by fire, use Aux Feeduater Pp 1-1 or 1-3
)
1 8.0 Fire Area A8-1 (Fire Zone 3-F)
I Containment Spray Pump Room Reciprocating Charging Piamp 1-3 If damaged by fire, use centrifugal charging pump 1-1 or 1-2.
6 I
l 1
i l
l DC0275 291 l
t I
I
4 w.
Appendix 3 Page 7 of 41 EP M-10 Fire Protection of Safe Shutdown Equipment Arttuto ERllReff ALTBNLTIVE EQUIRefTM RATOR ACTIONS 9.0 Fire Area 3-H-1 Charging Pump 1-1 and 1-2 Room. 73' Elevation 9.A) 8803A BIT inlet valve Use normal CVCS charging path for boration.
88038 BIT inlet valve j
9.8)
Reciprocating Charging Pump 1-3 control All three pumps can be fire damaged. But it is possible to bypass the control circuitry for pump 1-3 in the 4KV i
switchgear room, and manually close the 4KV breaker to
]
start the reciprocating pump. Refer to Step 4 of main 3
procedure.
9.C) Charging pump 1-1 and 1-2 power and control Same as item 9.B above, i
10.0 Fire Area 3-H-2 i
\\
j Reciprocating Charging Pump 1-3 Room, Aux Bldg. 73' Elevation l
10.A)
Reciprocating charging Pp 1-3 Use centrifugal charging Pp 1-1 or 1-2 l
l 11.0 Fire Area AB-1 (Fire Zone 3-J-1)
Component Cooling Water Pp 1-1 Room. 75' Elevation 4
i 11.A) Control circuit to Diesel 1-2 and 1-3 Diesel 1-3 normal control circuit, and Diesel 1-2 backup i
control circuit may be fire damaged. If so, switch to j
alternate control circuit locally at the diesel generator i
- rooms, i
DC0275 30!
7_
i l
mm..
Appendix 3 Page 8 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment g
i AFFECD EQUIReff ALTEllNATIVE EDVIRENTMERATOR ACTIONS i
I 11.8) Diesel Fuel Oil Transfer Pump 0-2 Circuit for pump 0-2 is protected by a 2-hour fire barrier l
and should not be affected by a fire. Circuit for pump 0-1 j
is not protected.
]
11.C) Aux Feeduater Pump 1-3 Use AFW p 1-1 if p 1-3 is fire damaged.
p p
i 11.D) AWS Pump 1-2 Exhaust Fan E-101 Use ASW Pump 1-2 and its exhaust fan E103 as alternate safe shutdown equipment.
11.E) CCW Pp 1-1 Use CCW Pp 1-2 and 1-3 1
I j
12.0 Fire Area AB-1 (Fire Zone 3-J-2) 2 Component Cooling Water Pump 1-2 Room. Elevation 75 l
12.A) Boration Path i
8803A BIT inlet valve Continue to use normal CVCS charging path for boration.
88038 BIT inlet valve 12.B) Component Cooling Water Pump 1-1 and 1-2 The auxiliary lube oil pump control for CCW Pp 1-1 and 1-2 j
aux lube oil pumps, may be fire damaged. Use CCW Pp 1-3. or locally start CCW Pp i
1-1 and 1-2 at 4KV breakers. Refer to Step 4 of main j
procedure.
l 12.C) Charging Pumps 1-1,1-2 and their aux lobe oil The circuitry for auxiliary lobe oil pumps for charging pumps l
pumps, reciprocating charging Pp 1-3 control.
1-1 and 1-2 may be fire damaged. Without the auxiliary lobe oil pumps, these pumps cannot be started from the Control Room or Hot Shutdown Panel. Therefore, if they are needed, i
start them locally at 4 KV switchgear rooms. Refer to Step 4 of main procedure. If reciprocating charging pump is lost.
l use centrifugal charging pump 1-1 and 1-2.
I
_ DC0275 31!
1 f,,. _ _
- +
w.
Appendix 3 4
Page g of 41 EP M-10. Fire Protection of Safe Shutdown Equipment htutu EQUIROE N.TEl51ATIVE EQUIROR/0 RATOR ACTIONS 2
12.D) Diesel 1-2 backup control Verify and continue to use nomal control power to Diesel 1-2 Diesel 1-3 output breaker trt,9 selected at diesel generator room. If diesel 1-3 trips.
verify diesel 1-1 and 1-2 available.
1 13.0 Fire Area AB-1 (Fire Zone 3-J-3) i Component Cooling Water Pump 1-3, Aux B1dg. 75' Elevation 13.A) Boration Path j
8803A - BIT inlet valve Use nomal CVCS charging path for boration.
88038 - BIT inlet valve 13.8) CCW Pp 1-3 Use CCW Pp 1-1 and 1-2.
i i
13.C) Charging pumps 1-1,1-2 and their aux lube oil The circuitry for the auxiliary lube oil pumps for charging pumps, reciprocating charging pump 1-3 control.
pumps 1-1 and 1-2 may be fire damaged. Without the auxf11ary lube oil pumps, these pumps cannot be started from the Control Room or Hot Shutdown Panel. Therefore, if they are i
needed, start them locally at 4 KV switchgear rooms. Refer ta Step 4 of main procedure. If the reciprocating charging 4
pump is lost, use centrifugal charging pump 1-1 and 1-2.
i 14.0 Fire Area AB-1 (Fire Zone 3-I.)
Boric Acid and Waste Evaporator Area, 85' Elevation 14.A) Charging and boration flow path and equipment.
i j
DC0275 32I
h.
Appendix 3 EP M-10. Fire Protection of Safe Shutdown Equipment 4
MTECTS EDUlF9ENT ALTERNATIVE EDUIF99fTA)FERATOR ACTIONS 4
i i
1.
Valve 8805A RWST suction If 8805A and 8 cannot be opened electrically, use manual 88058 RWST suction handles provided for the valves. If 8104 is damaged.
j 8104 Emerg. borate continue to use normal boration path, or the manual bypass 4
valve 8471 around 8104, if FCV 110A is open.
l 2.
Boric Acid Transfer Pp 1-1 and 1-2 If both boric acid transfer pumps are fire damaged, borate i
via 8805A and 8. or inject the BIT.
9 3.
Charging Pp 1-2 aux lube oil Pp Use charging Pp 1-1, 1-3 or locally start pump 1-2 at 4 KV switchgear room. Refer to Step 4 of main procedure.
i
}
14.8) Aux Feedwater Pp 1-3 Use Turbine Driven Aux Feedwater Pp 1-1, if MD AFW Pp 1-2 and i
i Aux Feedwater Pp 1-2 1-3 are unavailable. (Note the circuits for pump 1-2 and 1-3 l
are provided with a 2-hour fire barrier in this fire zone).
4 i
i 15.0 Fire Area V-1 (Fire Zone 3-P-3)
Aux 81ds Main Exh Fan Room #2.115' Elevation i
Aux Bldg Normal Exh Filter Room.100' Elevation Aux Bldg Normal Concrete Exh Duct. 93' Elevation, and Plenum 85' Elevation
)
Aux Feedwater Pp 1-3 Use Turbine Driven Aux Feedwater Pp 1-1.
l Aux Feedwater Pp 1-2 f
16.0 Fire Area 3-0-1 i
Aux Feedwater Turbine Driven Pump 1-1 Turb driven AFW Pp 1-1 Use. motor driven AFW Pp 1-2 and 1-3 i
j e
. DC0275 331 l
h.
Appendix 3 Page 11 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTS EQJIPPUIT M.TEINATIE EQJIPP0(TAFERATIR ACTIG6 1
17.0 Fire Area AB-1 (Fire Zone 3-0-2)
Aux Feedwater Motor Driven Pumps AFW Pp 1-2 and 1-3 Use turbine driven AFW Pp 1-1 i
- 18. Fire Area 48-1 (Fire Zone 3-X)
Boric Acid Transfer Pumps and CVCS Demins. 100' Elevation Boration Flow Path 1.
Valve 8805A - RWST suction If 8805A and B cannot be opened electrically, use manual 88058 - RWST suction handles provided for the valves. If 8104 is damaged.
8104 - Emerg barate continue to use normal boration path, or the manual bypass
. valve 8471 around 8104, if FCV 1104 is open.
2.
Boric Acid Transfer Pp 1-1 and 1-2 If both boric acid transfer pumps are fire damaged, borate via 8805A and B (use manual handles if necessary), or inject the BIT.
19.0 Fire Area AB-1 (Fire Zone 3-AA)
Boric Acid Tanks. Aux Bldg. 115' Elevation Boration Flow Path i
1.
Valve 8805A - RWST suction If 8805A & B cannot be opened electrically, use manual 88058 - RWST suction handles provided for the valves. If 8104 is damaged.
8104 - Emerg borate continue to use normal boration path, or the manual bypass valve 8471 arcund 8104, if FCV 110A is open.
DC0275 34!
- b..
Appendix 3 Page 12 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AH-tutu EQUlFENT ALTElWATIVE EQUlFE NT/0 RATOR ACTIONS 2.
Borate Acid Tank 1-1 and 1-2 level Use boric acid flow integrator and control operator log to indication Lt 102 and 106.
determine boric acid tank level. Notify IAC to set up temporary level indication for the tanks.
20.0 Fire Area 3-BB (A. Penetration Area 115';
8.
Penetration Area 100'; C.
PenetrationArea.85')
20.A) Penetration Area. 115' Elevation. Aux Bldg 1.
Diesel 1-1 Normal control power for Diesel 1-1 may be fire damaged. If so, select backup control power at diesel generator room. In addition, diesel 1-2 and 1-3 are available.
l 2.
Aux Feedwater Level Control Valves LCV 113 LCV 110 and LCY 111 from AFW Pp 1-2 supply is available.
LCV 115 They are not affected by fire at this elevation.
LCV 108 FCV 37 Fire in this area could fall these three valves (LCV 113. 115 FCV 38 and 108) only in the OPEN position. The capahtlity to FCV 95 modulate these valves may be lost. If so, modulate auxiliary feedwater flow locally using handwheels provided at the valves. However, valve modulation may not be needed since it's associated AFW Pump (s) may not be running. In addition.
there are check valves downstream which will prevent reverse water flow.)
3.
Charging and Boration 8104 - Emerg boration valve Use manual bypass valve 8471 around 8104 f f FCV 110A is open.
Or use supply from RWST via 8805 A and B DC0275 35I l
y
9 tems. =
Appendix 3 Page 13 of 41 EP M-10 Fire Protection of Safe Shutdown Iquipment htuw EDUIFPENT M.TEINATIVE EQUIFPENT/0PERATOR ACTIONS HCV - 142 If fire damaged the capability to modulate this valve, use the duplicate control at the hot S/D panel, (using backup nitrogensupply) 88018 - BIT outlet Use 8801A a
8145 - PZR Aux Spray For depressurization of RCS, use PZR PORV 474 (which is i
8148 - PZR Aux Spray Bypass sufficiently separated from these valves) [if RCPs are not running. If RCPs are running, try the normal PZR spray valves, or the manual PZR spray valves bypass inside containment.]
If 8145 or 8148 fall open due to hot short, terminate premature RCS depressurization using 8107 or 8108. These valves are not affected by fire at this elevation.
8146 - Nomal Charging Fire at this elevation cocid cause both these valves to fail 8147.- Alternate Charging close. If so, use charging via
- 1) Manual bypass valve 8969 around the Bli l
- 2) or charge through the BIT 4.
CCW to the RHR HX FCV 364 If the control circuits for these valves are fire damaged.
FCV 365 they can be opened or closed using handwheels provided for the valves.
5.a 101 Steam. Dump Valves If fire damaged the capability to operate these valves from V8-3, go to the hot shutdown panel to operate them.
Otherwise, manually operate these valves using handwheels provided. Analysis indicates that these valves cannot fail open.due to hot short or short to ground resulting from a fire in this area.
[ ] Statements enclosed are not part of Appendix R Review DC0275 361 C
f
~l- - - - -
Appendix 3 Page 14 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment Antuw EQUIPENT ALTERNATIVE EQUIPENT/0RRATOR ACTIONS 5.b Steam Generator Blowdown Valves Inside If these valves failed open due to a fire in this area.
Containment isolate the corresponding outside containment blowdown isolation valve.
FCV 760 FCV 761 FCV 762 FCV 763 5.c Steam Generator Level Transmitter Fire in this elevation may have damaged the steam generator LT's. At least the level transmitter ending in 7's or 9's (LT 517, S'l, 537, 547 and LT 519, 529, 539, 549) should e
still be available, due to their physical seperation one another.
5.d Steam Generator Pressure Transmitters At least one of the following groups of steam generator pressure transmitters should still be available after a fire in this area:
Group A: PT 514 S.G. #1 PT 524 S.G. #2 Group B: PT 515 S.G. #1 PT 525 S.G. #2 Group C: PT 536 S.G. f3 PT 546 S.G. #4 6.a Pressurizer PORV's and block valves A fire at this elevation can cause at most two PORV': to fail close, and the block valves to fall as is, normally open. In PCV 474, 8000A addition aux spray valve 8145 will be available. Therefore, PCV 456, 80008 either 8145 or the available PDRV (474 or 455c and 456) can PCV 455C, 8000C be used to depressurize the RCS. [When using aux spray, secure norsal and alternate charging.]
[ ] Statement enclosed not part of Appendix R Review DC0275 37I
- h..
Appendix 3 Page 15 of 41 EP M-10 Fire Protection of Safe Shutdown Equipment g
Arttutu EQUlFENT ALTEINATIVE EQUIFTENT/0FERATOR ACTIONS However, following a fire, a hot short could occur when the operator operates (opens) the PZR aux spray valve 8148 resulting in the scurious opening of PORV 455C. [Therefore the operator may want to attempt closing block valve 8000C before opening 8148, or not use it at all]
6.b Pressurizer Level Transmitters At least one of these pressurizer transmitters should still be available following a fire at this elevation.
LT 459 LT 461 6.c RCS Wide Range Temperature Either loop 1 and 2 or loop 3 and 4 temperature element should still be available following a fire in this area.
Loop 1 413A(hotleg) 4138(coldleg)
Loop 2 423A 4238 Loop 3 433A 4338 Loop 4 443A 4438 7.
RHR hot leg injection isolation The fire could cause a hot short in the control circuit valve 8703.
resulting in prenature opening of this valve. However, there are two series check valves downstream which will prevent the RHR piping from being pressurized.
8.
Source Range Monitors At least one source range monitor should still be available.
NE 31 NE 32
[ ] Statements enclosed are not part of Aplendix R Review DC0275 381
Eben.
- Appendix 3 Page_20 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECD EDUIFENT ALENATIVE EQUlFENTA)PERATOR ACTIONS 2.
Aux Feedwater System The steam supply valve FCV-95 to turbine driven AFW pump may be fire. damaged. However, motor driven AFW Pp 1-2 and 1-3 should still be available, althou LCV 110 (AFW Pp 1-2 to S.G. #1)) gh the ability to modulate j
and LCV 111 (AFW Pp 1-2 to S.G. #2) may be lost. In that case, handwheel modulation i
will be required for LCV 110 and 111. At any rate, LCV 110 i
and 111 can fall only in the OPEN position. This is up to 4
I the operator's option since LCV 115 and 113 are unaffected and would be available with AFW Pp 1-3.
3.
Diesel 1-1 Normal DC control power may have been damaged by fire. If so, select backup control power at local diesel control panel. In addition, Diesel 1-2 & 1-3 are available.
4.
CCW to RHR HX If the control circuits for these valves are damaged by fire, the valves can be operated using handwheels provided.
Steam Generator Pressure Transmitter Steam Generator 1-1 pressure transmitter PT 514 may have been damaged by fire. All other steam generator pressure transmitters are not affected by a fire in this area..
6.
RCS Wide Range Pressure Transmitters RCS wide range pressure transmitters PT 403 and PT 405 may be fire damaged. However, PT 406 should still be available.
DC0275 431
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- Appendix 3 Page 17 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment Antuw EQUlFENT ALTERNATIVE EQUIFMNT/0RRATOR ACTIONS 3.
Charging and Boration 8104 - Emerg boration Use manual bypass valve 8471, if FCV 110A is (, pen; or 8805 A and B - supply from RWST.
8107 - Charging line iso valve They are fail as-is valve, that is, when damaged by fire 8108 - Charging line iso valve during at power condition, they will remain open.
8145 - PZR Aux Spray If this valve hot shorts open, isolate using HCV 142 or 8108.
These two valves (circuits) are sufficiently separated from each other to preclude concurrent damage by a single fire in this area. When RCS depressurization is required, use 8148, (aux spray valve bypass). [Whenauxs normal and alternate charging valves.] pray is used, secure 8146 - Nomal Charging (loop 4)
When damaged by fire 8146 and 8147 can fail either open or 8147 - Alternate Charging (loop 3) closed. [The fail open position is not of concern since 8801A - BIT cutlet charging flow would not be affected.] If they fail close, 88018 - BIT outlet RCS boration can be accomplished via the BIT bypass manual valve 8969. The same fire would also likely damage circuits for valves 8801A and B.
Therefore, in order to borate using the BIT, the handwheels provided for the valves must be used.
HCV - 142 If damaged by fire, this valve is designed to fail closed.
Attempt to operate this valve from Hot S/D panel. In the event of a premature RCS depressurization due to spurious aux spray valve operation, at least one of the three valves HCV 142, 8107 or 8108 should be available to isolate aux spray.
Sufficient fire seperation exists between HCV 142 8 8108.
4.
CCW to RHR HX If the control circuits for these valves are fire damaged, they can be opened or closed using handwheels provided for FCV - 364 the valves.
FCV - 365
[ ] Statements enclosed are not part of Appendix R Review DC0275 401
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Appendix 3 Page 17 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment httutlj EQUIRENT ALTERNATIVE EDUlFENT/ORRATOR ACTIONS i
i 3.
Charging and Boration j
8104 - Emerg boration use manual bypass valve 8471, if FCV 110A is open; or 8805 A j
and 8 - supply from RWST.
8107 - Charging line iso valve They are fall as-is valve, that is, when damaged by fire j
8108 - Charging line iso valve during at power condition, they will remain open.
8145 - PZR Aux Spray If this valve hot shorts open, isolate using HCV 142 or 8108.
l These two valves (circuits) are sufficiently separated from 8
each other to preclude concurrent damage by a single fire in this area. When RCS depressurization is required, use 8148, 1
(aux spray valve bypass). [When aux s j
normal and alternate charging valves.] pray is used, secure i
8146 - Normal Charging (loop 4)
When damaged by fire 8146 and 8147 can fall either open or j
8147 - Alternate Charging (loop 3) closed. [The fail open position is not of concern since 8801A - BIT outlet charging flow would not be affected.] If they fail close.
l 88018 - BIT outlet RCS boration can be accomplished via the BIT bypass manual i
valve 8969. The same fire would also likely damage circuits for valves 8801A and 8.
Therefore, in order to borate using the BIT, the handwheels provided for the valves must be used.
HCV - 142 If damaged by fire, this valve is designed to fail closed, i
Attempt to operate this valve from Hot S/D panel. In the event of a premature RCS depressurization due to spurious aux spray valve operation, at least one of the three valves HCV 142, 8107 or 8108 should be available to isolate aux spray.
Sufficient fire seperation exists between HCV 142 8 8108.
4.
CCW to RHR HX If the control circuits for these valves are fire damaged, they can be opened or closed using handwheels provided for I
FCV - 364 the valves.
FCV - 365
[ ] Statements enclosed are not part of Appendix R Review i
DC0275 40I e
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Appendix 3 Page 19 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment Antuto EQUlFPENT ALTEMATIVE EQUIF90fr/0FERATOR ACTIONS 6.a Pressurizer PORV's and Block Valves A fire at this elevation can cause the PORV's to fall close, 1
and block valves to fail as is. Therefore, PORV's failure i
PCV 474.' 8000A should not cau:;e a RCS pre-mature depressurization. However, i
PCV 456, 8000B the same fire at this elevation could hot short pressurizer PCV 455C, 8000C aux spray valve 8145 causing it to spuriously open thus prematurely depressurizing the RCS. If that occurs, use one of the three valves 8107, 8108 or HCV 142 (at the hot S/D panel if needed) to isolate aux spray. When RCS depressurization is required to bring unit to cold shutdown, open the above valve that was closed to provide the needed spray via the fail open aux spray valve 8145.
i l
6.b Pressurizer Level Transmitters LT 459 and LT 461 should still be available. They are not affected by a fire in this area.
I 6.c RCS Pressure Transattters PT 403 should still be available. The others (PT 405 and PT 406) may have been damaged by the fire, 6.d RCS Wide Range Temperature Elements Loop 2 hot and cold leg wide range temperature elements (TE-423A & B) should still be available. TE's from other
]
loops may have been fire damaged.
I l
20.C)
Penetration Area, 85' Elevation i
j 1.
Charging and Boration The charging line and isolation valve 8108 ff damaged by fire l
will fall as is, which does not pose a problem. HCV-142 can HCV - 142 fall closed. If so, control should still be available from the hot S/D panel. If 8805A and B are fire damaged, use the 8108 - Charging line iso-valve handwheels provided for the valves. Also, valve 8104 is still available. It is not affected by a fire at this j
8805A and B - RWST supply elevation.
l l
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Appendix 3 Page 16 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment g
AFttutU EIEIFENT ALTERNATIVE EDUlFPENTA)PERATOR ACTIONS 3
1 20.8)
Penetration Area, 100' Elevation 1.
Diesel 1-1 Normal control power for Diesel 1-1 may be fire damaged. If so, select backup control power at diesel generator room. In j
addition, Diesel 1-2 and 1-3 are not affected by this fire.
)
2.
Steam Supply to AFW Pp 1-1 Turbine, and j
AFW Level Control Valves FCV-37 S.G. #2 to AFW Pp Turb use motor driven pumps 1-2 and 1-3.
Depends on the location i
FCV-38 S.G. f3 to AFW Pp Turb of the fire. AFW TD pump train may be available.
FCV-95 Steam supply to AFW Pp Turb LCV - 107 TD AFW Pp to S.G. #2 LCV 107 and LCV 108 if damaged by fire will fati only in the I
LCV - 108 TD AFW Pp to S.G. #3 OPEN position. The same fire may also cau:;e FCV 37, 38 and 1
LCV - 110 MD AFW Pp 1-2 to S.G. #1 95 to fall as-is (closed). Therefore, no flow is expected LCV - 111 MD AFW Pp 1-2 to S.G. #2 from the turbine driven AFW Train. LCV 110, 111, 113 and 115 LCV - 113 MD AFW Pp 1-3 to S.G. f4 when damaged by a fire in this area, can fati only in the LCV - 115 MD AFW Pp 1-3 to S.G. #3 OPEN position. Since the motor driven AFW pumps are not affected AFW flow is assured through these LCV's. However, in order to modulate flow, the operator must resort to the handwheels provided for at the valves. Local valve modulations is at the options of the operator since the engineering analysis demonstrated that there is adequate seperation between the redundant trains of the LCV's, depending on the location of the fire. Either AFW TD train (LCV 107, FCV 38 and FCV 95) or AFW MD Train 1-2 (LCV 110, 111, AFW Pp 1-2) or AFW MD Train 1-3 (LCV 113, 115, AFW Pp 1-3) would be available and controllable from the Control Room.
DC0275 39I M
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Appendix 3 Page 21 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EQUllMNT ALTElWATIVE EQUIFENT/0FERATOR ACTIONS 21.0 Fire Area 4-A Counting and Chemical 1.aboratory Aux Butiding Elev 85 This entire fire area can be grouped under six "sub-areas' or "sub-spaces" as follows:
21.A)
The north wall 21.8)
The south end of the west wall
~
21.C)
The space above the drop ceiling of the counting room.
21.D)
The space above the drop ceiling of the chemistry engineer office.
21.E)
The space atove the drop ceiling for the balance room.
21.F)
The space above the drop ceiling of the laboratory and storage room.
21.A)
Shutdown Functions along the North Wall i
- 1) 480 volts, Bus F Fire Protection Review concluded that sufficient fire protection has been provided to these equipment such that,a
- 2) Diesel 1-2 and 1-3 postulated fire in this area will not adversely affect their functions. Nevertheless, the equipment are listed here to i
alert the operators of the possibility.
- 3) Centrifugal charging pump 1-1 and its aux lube oli pump
- 4) CCW pump 1-1 and its aux lube oli pump DC0275 44I I
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Appendix 3 Page 22 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment
.i AFFECD Eulli+ENT ALTEltlATIVE EQUlFPENT/0PERATOR ACTIONS 5). Motor driven AFW pump 1-1 and its LCV 113 and 115
- 6) Aux Saltwater Pump 1-1
- 7) BIT inlet valve 8803A
]
21.8)
Shutdown Functions at the South End of i
of the West Wall
CCW HX 1-2 outlet valve FCV 431
21.C)
Shutdown Functions above the Drop Ceiling of the Counting Room
- 2) Diesel fuel oli transfer pump 0-2
}
- 4) 480 volts vital load center, IF l
l 1
DC0275 451
Appendix 3 Page 23 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFEC D BAJif90fT ALTEFWATIVE E(111F99frA) RATOR ACTIONS l
l 21.D)
Shutdown Functions above the Drop Ceiling of l
Chemical Engineer Office
CCW HX 1-2 outlet valve FCV 431
- 2) Diesel Fuel oli transfer pumps 0-1 and 0-2
- 3) Boric acid transfer pump 1-1 l
and RWST supply valve 8805A i
21.E)
Shutdown functions above the Drop Ceiling of Balance Room j
- 1) 480 volts vital load center, IF See comunents for item 21.A above.
480 volts vital load center, IG 1
21.F)
Shutdown Functions above the Drop Ceiling of the Laboratory and Storage Room
- 2) Boric acid transfer Pp 1-1 and 1-2 i
8805A(RWST I
88058 (RWST 8104 Emerg boration valve j
- 3) Diesel fuel oil transfer j
Pp 0-1 and 0-2 j
- 4) 480 volts vital load center, IG 480 volts vital load center, 1H DC0275 461 Oe
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Appendix 3 Page 24 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EllllFPDfT ALTERNATIVE EQUIFENTA)PERATOR ACTIONS
- 6) Power (Bus F) to Unit 1 Control Room ventilation, and power (Bus H) to Unit 2 i
Control Room ventilation l
i 22.0 Fire Area 4-A-1 G.
Bus Compartment Next to Chem Lab and Counting Room. Aux Bldg. 85' Elevation 22.A) 480 V Vital Load Center. IG A fire in this area could damage the Bus G safeguard equipment listed to the left. Bus F and H are not affected.
l 22.8) Diesel 1-1 and should still be available. For diesel 1-2 if backup Diesel 1-2 (backup control power only) control power is lost, continue to use the normal control 22.C) Centrifugal Charging pump 1-2 and its aux lube oli pump
{
22.D) CCW Pp 1-2 and its aux lube oil pump 22.E) ASW Pp 1-2 I
l 22.F) BIT inlet valve 88038 22.G) Diesel fuel oil transfer p 0-2 p
22.H) RHR pump 1-1 3
DC0275 47I
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Appendix 3 Page 25 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment 9
htuts EQUIPPENT ALTERNATIVE EQUHTENTMERATOR ACTIONS 23.0 Fire Area 4-A-2 H.
Bus Compartment Next to the Laboratory, Aux Bldg. 85' Elevation 23.A) 480 V vital loed center, I H A fire in this area could damage the Bus H safeguard equipment listed to the left. However, redundant trains Bus 23.B) Diesel 1-1 F and G are not affected, and should still be available. For Diesel 1-3 (Backup control power only) diesel 1-3, continue to use normal DC control power.
23.C) CCW Pp 1-3 and its aux lube oil pump 23.0) MD AFW Pp 1-2 and its LCVs 110 and 111 i
23.E) Diesel fuel oil transfer pump 0-1 4
23.F) RHR pump 1-2 4
i i
24.0 Fire Area 4-B
?
Showers Lockers and Access Control, Aux Bldg. 85' Elevation 24.A) FCV430(CCWfromCCWHX1-1)
One of these two valves are normally open at power. Since
)
FCV 431 (CCW from CCW HX 1-2) they are fail as-is valves, at least one valve will be in the open position following a fire in this area.
l 24.8) FCV 602 (ASW to CCW HX 1-1)
There is a possibility that a fire in this area could cause a FCV 603 (ASW to CCW HX 1-2) hot short to the control circuits of these valves causing them to fall closed. If that is the case, manually open the valve (s) by removing the air supply locally.
i 24.C) Diesel fuel oil transfer pump 0-1 and 0-2 Circuitry for Pump 0-2 is provided with a 1-hour fire barrier and should be available for service.
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Appendix 3 Page 26 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment htutu EQUIPENT ALTERNATIVE EQUIRENTA)FERATOR ACTIONS i
24.D) Diesel 1-2(control)
Verify and continue to use nomal de control for diesel i
Diesel 1-3 (control) generator 1-2.
In additton, diesel generator 1-1 is available.
24.E) Ventilation Exhaust fan E101 for ASW pump Circuit for this fan is provided with a 1-hour fire barrier 1-2.
and should be available for service.
25.0 Fire Area 5-A-1, 5-A-2 and 5-A-3 480V Vital Switchgear Rooms (F. G & H Buses) Area H.100' Elevation i
25.A) Emergency power supply Verify redundant equipment from the alternate buses are availabb.
i Also, a fire in any one of these areas could have damaged the control power to the diesel corresponding with the bus, and in addition, the backup control power, and power to the lube oli heater to one of the remaining diesels.
25.8) Steam generator blowdown inside containment If these valves spuriously open due to fire damage, close its isolation valves corresponding outside containment steam generator blowdown isolation valves.
FCV760and761(FireArea5-A-2)
FCV 762 and 763 (Fire Area 5-A-3) 1 DC0275 491
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Appendix 3 Page 27 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment AFFECTED EDUlFMNT ALTERNATIVE EQUlFENT/0KRATOR ACTIONS 26.0 Fire Area 5-A-4 Hot Shutdown Panel Area and Non-Vital 480V Switchgear Room Area H, 100' Elevation I
26.A) Aux Feedwater System 1
LCV 113 and 115 MD AFW Pp 1-3 The motor driven pumps may have been damaged by the fire.
2 LCV 110 and Ill, MD AFW Pp 1-2 The LCVs for the motor driven trains may have been damaged by 3
LCV 107 and 108 and FCV 95 (TD AFW Pp the fire in their open position. If the motor driven pumps 1-1) are damaged, use the turbine driven pump. If the motor driven pumps are operable, but their LCVs have lost their modulation ability, modulate AFW flow using handwheels provided for the valves. If the TD AFW Pp 1-1 is the only means to feed the steam generators, and AFW flow modulation is required, manual modulation is available using handwheels provided for the valves.
26.B) FCV602(ASWtoCCWHX1-1)
There is a possibility that a fire in this area could cause a FCV 603 (ASW to CCW HX 1-2) hot short to the control circuits of these valves causing them to fail close. If that is the case, manually open the valve (s) by removing the air supply locally.
26.C) Boric acid transfer pump 1-1 Engineering review indicates centrifugal charging pump 1-2, Boric acid transfer pump 1-2 boric acid transfer pump 1-2, and emergency boration valve Centrifugal charging pump 1-1 should still be available following a fire in this area as Centrifugal charging pump 1-2 the circuits for this equipment is associated with their Emerg boration valve 8104 operation from the hot shutdown panel only.
l 26.D) CCW pump 1-1 Engineering reviews indicates fire in this area could damage CCW pump 1-2 CCW Pp 1-1 and 1-3, FCV 430 and 431. However, CCW Pp 1-2 CCW pump 1-3 should still be available. Also, since one of the FCV's are FCV430(CCWtoCCWHX1-1) normally open, sufficient flow path exists for the CCW system i
FCV 431 (CCW to CCW HX 1-2) to provide adequate shutdown capability. The FCV's are motor operated valves and they fail in the as-is position.
l l
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Appendix 3 Page 28 s'
41 EP M-10 Fire Protection of Safe Shutdown Equipment AFFECTED EQUlF9ENT ALTERNATIVE EQUlFENT/0PERATOR ACTIONS 26.E) Diesel 1-2 backup control circuiting Verify and continue to use diesel 1-2 control power from the normal DC supply.
~
l 26.F) Instrumentation System
- 1) Steam generator' pressure transmitter Use redundant pressure transmitters for affected steam PT 514, 524, 534 and 544.
generators.
- 2) RCS wide range temperature, loop 3 and 4.
Use loop 1 and 2 RCS wide range temperature indications.
- 3) PZR level LT 459 and 460 Use pressurizer LT 461 and l'T 406 (cold calibrated).
26.G) Ventilation System Exhaust E101 for Aux Salt Water Pp 1-2 The exhaust fan for ASW Pp 1-2 room may have been damaged by fire. If so, use ASW Pp 1-1 and exhaust fan E-103 for plant shutdown.
26.H) 10% Steam Dump Valves nitrogen and control If these valves cannot be opened pneumatically, use air (no electric circuit involved) handwheels provided for the valves.
27.0 Fire Area 6-A-1, 6-A-2, 6-A-3 Battery Inverter and DC Switchgear Rooms.115' Elevation 27.A) Emergency Power A postulated fire in any one of the DC switchgear rooms can damage all the vital equipment connected to that DC bus, and all the equipment receiving power from the instrument AC panels located in the room. Verify redundant equipment from alternate buses are available.
In addition, a fire in any one DC switchgear room will likely damage the backup DC control power for one of two remaining die.sel generators.-
l 9
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Appendix 3 Page 29 of 41 EP M-10 Fire Protection of Safe Shutdcwn Equipment AFFECTED EQJIPPENT ALTERMTIVE EQUIPENT/0PERATOR ACTIONS i
27.8) Main Steam System 105 atmospheric steam dump (power and A fire in this area may damage the control circuits for these control) PCV 19, 20, 21 and 22 valves from the control room. However, control from Hot Shutdown Panel should still be available.
Steam generator blowdown inside If fire damage causes these valves to spuriously open, close containment isolation valves FCV 760, their corresponding outside containment blowdown isolation 761, 762 and 763.
valves.
27.C)
PZR PORVs and block valves PORY 474, valve 80004 One of these three sets of valves may be affected by a fire PORV 4550, valve 80008 in any one DC Switchgear room. The remaining two flow paths PORV 456, valve 8000C should still be available. No. adverse hot short could cause the PORV's to prematurely open.
27.0) 480V Switchgear and Inverter Room Ventilation System Supply fan S43 Following a fire in a DC Switchgear room, verify continued Supply fan S44 ventilation is being supplied to non-affected DC Switchgear If necessary, open door (s) and provide portable fan (s) room.
to ventilate the remaining DC Switchgear rooms.
27.E) AFW System Verify the availability of redundant train if a fire took away the vitality of the room. However, for fire area 6-A-1, motor driven AFW Pp 1-3 and LCV 113 and 115 which feed S.G.
1-3 and 1-4 may be lost due to a fire in this area. Local i
action may be required to handwheel the FCV open. MD AFW Pp 1-2 and TD AFW Pp 1-1 should still be available. FCV-38 to TD AFW Pp 1-1 may have hot short failed in the closed position. Local action may be required to handwheel the FCV open.
DC0275 521 t
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Appendix 3 Page 30 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EQUlFE NT Al.1ERNATIVE EDUlFENTA)FERATOR ACTIONS l
27.F) RCS wide range temperature Verify the availability of redundant instrument train if a fire took away the vitality of the room. In addition, for fire area 6-A-1, loop 1 and 2 hot and cold leg temperature indication may be lost. However, Locp 3 and 4 should still be available.
l 28.0 Fire Area 6-A-4 Reactor Trip Switchgear and Rod Control Programmer Area Elevation 115' 1
28.A) PZR Aux Spray valve 8145 If fire damage causes this valve to fail closed, use its d
bypass 8149 which is not affected by a fire in this area. If a hot short occurs and cause the valve to prematurely open, use charging Ifne isolation valve 8107, 8108 or HCV 142 to 1
stop RCS depressurization. Should charging line become isolated, boration via BIT bypass or the BIT itself should still be available. [Whenever aux spray is (intentionally) used to depressurize the RCS, verify that normal and alternate charging valves are closed.]
j 28.8) FCV 364 CCW to RHR HX 1-1 Use RHR Train 1-2 FCV 365 (CCW to RHR HX 1-2) is not affected by fire in this area, i
28.C) PZR PORY 456 If fire damage causes this valve to fall open, use its block valve 8000C to isolate the flowpath.
28.D) 10% Steam Dump for S.G. #1 ar.d 4 The 10% atmospheric dump for S.G. #2 (PCV-20) and 3 (PCV-21) should still be available.
[ ] Statement enclosed is not part of Appendix R review.
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Appendix 3 Page 31 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment Atttuto EDUlFENT ALENATIVE EQUlFENTA)PERATOR ACTIONS 29.0 Fire Area 6-A-5 Electrical Area West of Battery Room,115' Elevation 29.A) Feedwater System Motor driven AFW Pp 1-3, Turbine driven AFW Pp 1-1 is not affected by a fire in this LCV 113 and 115 area, and should be available for use.
Motor driven AFW Pp 1-2 LCV 110 and 111 29.8) FCV602(ASWtoCCWHX1-1)
There is a possibility that a fire in this area could cause a FCV 603 (ASW to CCW HX 1-2) hot short to the control v.frcuits of these valves causing them to fall close. If that is the case, manually open the valve (s) by removing the air supply locally.
29.C) FCV 430 (CCW from CCW HX 1-1)
These are fail as-is valves. One of them is nomally open, FCV 431 (CCW from CCW HX 1-1) therefore at least one CCW HX will always be available.
29.D) 8146 - Normal Charging, Loop 3 The DC control power to these valves may be lost to a fire in 8147 - Alternate Charging, Loop 4 this area. If boration is required, use the BIT bypass, or the BIT itself.
29.E) Diesel 1-2 The backup DC control power to Diesel 1-2 may be lost due to a fire in this area. Verify and continue to use normal DC control power for starting diesel.
29.F) RCS Loop 3 and 4 Wide Range Temperature RCS Loop 1 and 2 wide range T-hot and T-cold are not affected TE 433 A&B by a fire in this area.
TE 443 A&B 29.G) 10% atmospheric steam dump Fire in thfs area could damage the control circutts for these PCV-19 steam dump valves from the control room. Use the control at PCV-20 the Hot Shutdown Panel; that circutt is not affected by a PCV-21 fire in this area.
PCV-22 DC0275 54I
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Appendix 3 EP M-10. Fire Protection of Safe Shutdown Equipment t
1 Arttutu EQUIFENT ALTERNATIVE EDUlfMNT/0RRATOR ACTIONS 30.0 Fire Area 7-A i
Cable Spreading Room. Elev. 128' Refer to EP OP-8 CONTROL ROOM INACCESSIBLITY for guidance to shutdown the plant.
l 31.0 Fire Area CR-1 (Fire Zone 8-C) l Control Room. Elevation 140' Refer to EP OP-8 CONTROL ROOM INACCESSIBILITY for guidance to shutdown the plant.
32.0 Fire Area 8-G l
Safeguards (SSPS) Room i
SSPS Train A and 8 When a fire occurs in the SSPS room, manually trip the I
reactor. Go to EP OP-0 REACTOR TRIP WITH SAFETY INJECTION i
for guidance (even if no auto SIS has occured), and/or follow the procedure for fire area 7A/CR-1.
1 i
I 33.0 Fire Area 10 1
12 KV Cable Spreading Room. 76' Elevation and 12 KV Switchgear Room. 85' Elevation 33.A) ASW Pp 1-1 and 1-2 and their associated At least one of these two ASW trains should still be exhaust fan E101 and E103.
available following a fire in this area.
l i
{
DC0275 SSI 4
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Appendix 3 Page 33 of 41 EP M-10 Fire Protection of Safe Shutdown Equipment i
AFFECTE'j EQJIFENT Al.TERNATIE EQJIPENTERATOR ETIE I
33.8) Cu Pp 1;1 and its aux lube all Pp At least two of these three pump sets should still be l
CCh Pp 1-2 and its aux lube oil Pp available.
i CCW Pp 1-3 and its aux lube oil Pp
)
33.C) Ventilation System 4KV Swgr Re, (Bus H)
At least two of three supply fans should still be available.
4 Supply fan, S-67 Open doors, and use portable fans for ventilation if needed.
4KV Swgr Rm (Bus F)
Supply fan, S-69
)
33.D) RHR Pp 1-1 and 1-2 At least one train should still be available.
t 33.E) Emergency Power
\\
Diesel 1-1, 1-2 and 1-3 At least two diesels, one fuel oil transfer pump and two 480V 1
Diesel F0 Transfer Pp 0-1 and 0-2 vital load centers should still be available.
l 480V vital load center F G & H i
34.0 Fire Area T8-1. TB-2. TB-3 (Fire Zone 11-A-1, 11-8-1, 11-C-1 Respectively) l Diesel Generator Rooms (F G & H), 85' Elevation i
Diesel 1-3 Verify the affected diesel generator is tripped, rolldown i
Diesel 1-2 fire door all the way closed, carbon dioxide flooding to the i
Diesel 1-1 diesel generator room activated. In addition, the following Fuel Transfer Pp 0-2 equipment may be lost:
i i
Fuel Transfer.Pp 0-1
)
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Appendix 3 Page 34 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment AFFECD Elllif9ENT ALTERNATIVE EDUllTENTA)RRATOR ACTIONS (1) Lub'e oil heaters for one of two remaining diesels (2) Backup DC control power to one of two remaining diesels (3)
Diesel Fuel Oil Transfer pump associated with the affected diesel i
35.0 Fire Area 11-D Corridor Outside Diesel Generator Rooms Diesel 1-1, 1-2 and 1-3 All three vital buses F, G and H power and control circuitry, and diesel generator auxiliary and support systems circuitry Diesel Fuel 011 Transfer run through this fire area. Due to the fire barriers Pp 0-1. LCV 88, 89 and 90 provided for the conduits, and due to the low combustible loading in this area, engineering review concludes that all 2
Diesel Fuel Oil Transfer of the equipment should still be available following a Pp 0-2, LCV 85, 86 and 87 postulated fire in this area. Diesel emergency stop pushbutton is not need for safe shutdown.
l Diesel emergency stop pushbuttons I
I i
l DC0275 57I 1
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- Appendix 3 Page 35 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment AFFECTED EllllPENT ALTERNATIVE EDUlF906/0FERATOR ACTIONS 36.0 Fire Area TB-4. TB-5 and TB-6 (12-A,13A; 12-B,13-B; and 12-C.13C Respectively) 4 KV Switchgear Rooms. F, G and H Buses 4KV Switchgear Each of the three fire zones houses the 4KV Switchgear for a Bus F, G and H single vitality. In no case is the switchgear for one vitality housed in the same zone as that for a redundant vitality. Based on that, one train of safe shutdown equipment should still be available following a fire in any one switchgear room.
I i
1 l
37.0 Fire Area 13-D l
Excitation Switchgear Room l
37.A) Ventilation ducts to 4KV Switchgear rooms A fire in this area could fall closed the ventilation dampers to the 4KV Switchgear rooms. Following a fire, verify dampers position if possible, and verify cooling air being i
l supplied from the 4KV cable spreading room (s) below through the floor grating.
37.8) 4KV Bus F. H, and G Auto Transfer A fire in this area can damage the circuits which provide l
auto transfer to Startup power upon loss of auxiliary power.
Engineering review indicates that a spurious transfer to i
startup due to hot short is not possible. Even though transfer to startup power may have been impaired, auto transfer to diesel should still be available. That feature is not affected by a fire in this area.
1 i
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I DC0275 58I c
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Appendix 3 Page 36 of 41 i
EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EDUlFENT ALTERNATIVE EQUlFPENT/DFERATOR ACTIONS 38.0 Fire Area 13-E l
4KV Switchgear Ventilation Fan Room (119' Elevation) and Air Intake Plenum (107' Elevation)
Supply fan S-69 to 4KV Bus F If the fan (s) are damaged, open doors (post fire watch), use portable fan (s) to provide switchgear cooling.
l Supply fan S-68 to 4KV Bus G j
Supply fan S-67 to 4KV Bus H t
t 39.0 Fire Area T8-7 (Fire Zone 14-A)
Turbine Building - Main Condenser. Feedwater and Condensate Equipment Area Motor driven AFW Pp 1-3, LCV 113 and LCV 115 Try MD AFW pumps. If they are damaged, use turbine driven AFW Pp 1-1.
It is not affected by a fire in this area.
Motor driven AFW Pp 1-2 40.0 Fire Area 14-E Component Cooling Water Heat Exchangers. Turb Bldg. 85' Elevation 40.A) FCV602(ASWtoCCWHXI-1)
There is a possibility that a fire in this area could cause a FCV 603 (ASW to CCW HXI-2) hot short to the control circuits of these valves causing them to fall close. If that is the case, manually open the valves by removing their air supply locally.
40.8) FCV430(CCWfromCCWHX1-1)
These are fall as-is valves. Analysis indicates that hot FCV 431 (CCW from CCW HX 1-2) short will not result in valve closure if open. Since one valve is always open at power, at least one CCW train would still be available.
- DC0275 591
me...
Appendix 3 Page 37 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment htutu EQUlFENT ALTEfWATIVE EQUlFENT/0FERATOR ACTIONS 41.0 Fire Area 28 Area,0utside the Plant North of Unit 1 Containment and North East of Unit 1 Turbine Building 41.A) 105 steam dump A fire in this area could result in valve closure, but would PCV19(S.G.#1-1) not cause spurious opening of valves. Regardless of the PCV 20 (S.G. #1-2) dama e to these valves, PCV 21 (S.G. #1-3) and PCV 22 (S.G.
- 1-4 should still be available.
41.B) AFW System Use motor driven AFW Pp 1-3 to feed S.G. #1-1 and S.G. #1-4.
LCV 110, LCV 111. LCV 107, FCV 37 This AFW train is not affected. A fire in this area could damage the control circuitry for LCV 110, LCV 111, and LCV 107. However, these valves could fall only in their OPEN i
positions (per engineering analysis). Since motor driven AFW Pp 1-2 which provides flow through LCV 110 and LCV 111 is not j
affected by the fire, this AFW train is still useable 4
l although valve modulation for LCV 110 and 111 may be lost.
If modulation is desired, use the handwheels provided for the valves.
i FCV 37 and LCV 107 are associated with the turbine driven AFW pump. FCV 37 is normally open and is a fail as-is valve.
Assuming the turbine driven AFW pump is running, it can still feed all four steam generators because LCV 107 can fall only in the OPEN position. However, manual (handwheel) operator action will be required to close it (LCV 107) when plant conditions require.
41.C) Steam Generator 1-1 and 1-2 pressure transmitters PT 514, 515, 516 Use steam generator 1-3 and 1-4 they are not affected by a PT 524, 525, 526 fire in this area.
I 4
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DC0275 601 i
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%me o Appendix 3 Page 38 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EQUIFENT ALTElWATIVE EQUIFE NT/0FERATOR ACTIONS 4
42.0 Fire Area 30-A-1 and 30-A-2 Aux Salt Water Pump Vaults 42.A)
Fire Area 30-A-1 Engineering reviews indicates one of the two ASW Pump trains ASW Pp 1-1, should be available. A fire in any one pump room should in Exhaust fan E-103 no way affect the redundant train.
Discharge pressure switch PS-185 42.8) Fire Area 30-A-2 ASW Pp 1-2 Exhaust fan E-101 Discharge pressure switch PS-186 43.0 Fire Area IS-1 (Fire Zone 30-A-5) i Circulating Water Pumps Area 43.A) Exhaust Fan E-103 Engineering reviews indicates one of these two ASW trains Discharge press switch PS-185 should be available following a fire in this area.
ASW Inlet Gate SW-1-9 Starter 43.B) ASW Pp 1-2 Exhaust fan E-101 Discharge press switch PS-186 ASW Inlet Gate SW-1-8 Starter i
DC0275 611 l
l l, - -.. -.
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Appendix 3 Page 39 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment g
Atttutu EQUIFMNT ALTEIWATIVE EQUlFfelT/0PERATOR ACTIONS 44.0 Fire Area 34 Roof Area at Elevation 140' above Aux Bldg and Pens' ation Area GE and GW Unit I and 2 10% Atmospheric Dump PCV 21 S.G. #1-3 Use PCV 19 (S.G. #1-1) and PCV 20 (S.G. #1-2). They are not PCV 22 S.G. #1-4 affected by a fire in this area.
l 45.0 Fire Area 35-A and 35-B Diesel Fuel Oil Transfer Pump Vaults No. 0-1 and No. 0-2 i
Diesel Fuel Oil Transfer Pump 0-1 and 0-2 A fire if started in one pump vault will not effect the i
remaining pump in the other vault. Hence, one diesel fuel oil transfer train should still be available.
l i
46.0 Fire Area AB-1 (Fire Zone S-3) q Stairwell in the Aux Bldg j
' Motor driven AFW Pp 1-2 Attempt to use these motor driven pumps for safe shutdown.
Motor driven AFW Pp 1-3 If they do not work due to fire damage, use turbine driven j
AFW Pp 1-1.
It is not affected by fire in this area.
k i
l j
DC0275 621 i
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Appendix 3 Page 40 of 41 EP M-10. Fire Protection of Safe Shutdown Equipment AFFECTED EQUIRDIT ALTElWATIVE EQUIFENTiORRATOR ACTIONS 47.0 Fire Area TB-4 (Fire Zone 12-A) 4KV F Bus Cable Spreading Roon
'j 47.A) 4KV Bus F A fire in this area will likely damage 4KV Bus F and disable all the safeguard equipment powered from the bus.
1 47.8) Motor driven AFW Pp 1-2 (Bus H)
A fire in this area could damage the ability of motor driven AFW Pp 1-2 to auto start on loss of both main feedwater pumps. Manual operator action may be required to compensate i
for this loss. Regardless, turbine driven AFW Pp 1-1 should still be available. It is not affected by a fire in this area.
47.C) ASW Pump 1-2 (Bus G)
This pump may not auto start at the loss of ASW Pp 1-1 on Bus F.
Manual operator action in the Control Room may be j
required to start the pump.
l 48.0 Fire Area TB-5.(Fire Zone 12-8) 1 4KV G Bus Cable Spreading Room
\\
48.A) 4KV Bus G Loss of this bus is likely if a fire occurs in this area.
However, Bus F and H should still be available.
1
]
48.8) ASW Pump 1-1 (Bus F)
This pump may not auto start at the loss of ASW Pp 1-2 (BusG). Manual operator action in the Control Room may be required to start the pump.
48.C) Diesel 1-3 The fire may have damaged the backup DC control power to this diesel. Verify diesel on normal DC control power.
1 I'
_ DC0275 63I l
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Appendix 3 Page 41 of 41 EP M-10, Fire Protection of Safe Shutdown Equipment httutu EQUIFENT ALTERNATIVE EQUIFENT/0FERATOR ACTIONS 49.0 Fire Area TB-6 (Fire Zone 12-C) 4KV H Bus Cable Spreading Room 4KV Bus H Loss of this bus is likely if a fire occurs in this area.
However, Bus F and G should still be available.
50.0 Fire Area TB-7 (Fire Zone 12-E)
Iso Phase Bus Duct Area 4KV Auto Transfer A fire in this ares could damage circuits that provide for Bus F, G & H auto transfer of the 4KV vital buses to startup power following the loss of auxiliary power. However, the transfer 4
to diesels should still be still available. Those circuits are not affected by this fire.
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PGwE_
DIABLO CANYON POWER PLANT 7,,,,,%T4 PROCEDURE ON-THE-SPOT CHANGE O
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TEMPORARY (yodow)- [2piration Date w Deserenent oPEtt A T # to t,-
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INSTRUCTIONS:
Complete Appropriate Columns l
1.) PROCEDURE PAGE CHANGED ADD PAGE DELETE PAGE NEW PAGE NUMBER J af 3 8
1 2.) ATTACHMENTS Attachment Number (Ir.clude all pages with dates changed to date of this OTSC) namnen ene cnnnes-
- 1. 'I g f 8 A.. p o t e d e r * % vek'v*attd les af t(8 l-8w t
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uo initial otstribution if '[5. ortgnator ust distribut. to ' Control
'tade tv-List other initial distribution t_o Controlled Copy Holders of this procedure 5g o.t.n b, w C.ntr.i
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DeAaLO CANYON POWER PLANT UNIT AS) 1 AND 2 ON T
OATE PAGE 2 0F 3 me FIRE PROTECTION OF SAFE SHUTDOWN EQUIPMENT There are more fire zones in the plant than is addressed in this
( { procedure.
The reason why certain fire zones are not in luded in this d
procedure is because those zones do not contain safe s down circuits in them.
PROCEDURE 1.
If a fire occurs in the plant the following additional procedures should be used immediately:
Non-radiological Fires - Volume 3 in the Plant Manual.
a.
Emergency Procedure M-6 ej b.
Radiological Fire
- Volume 3 in the Plant Manual.
Emergency Procedure R-6
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- 55. 51$5_b'2!i$' i[Ni "
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2.
The DETECTOR ZONES (listed in the Fire Plan) do not coincide with the FIRE AREA 5 (ZONES) defined in this procedure. Once the location of the fire is known, determine which area (zone) it is in by referring to Appendix 1 of this procedure.
E: Not all fire zones are equipped with fire / smoke detectors.
}
3.
After identifying the affected fire area (zone), follow the guidelines in Appendix 3 of this procedure to maintain the operability of the safe shutdown equipment.
4.
In Appendix 3 of this procedure, whenever the instructions call out for manually closing pump breakers for CCW or charging pumps, be aware that there are dedicated wrenches available in the 4KV I
switchgear rooms that can be used to open the switchgear doors.
The instructions to manually close the pump breaker are posted inside the door.
5.
Whenever mariual valving is performed on a motor operated valve, the power supply for the valve should be tripped off at the 480 i
i volts load center.
i DC0275 21 6
i
- -. _ - - -. - _ _.... _. - _. -. - - - _. - - _ _ - - -. - _. _ _ - _ _ _ _, _ _ _ _ _ -. - - _.. ~ - _ _, _ _ _ _. -. -
t-
l l
l PGandE Letter No.: DCL-84-268 CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3B TITLE REV OR-1 Offsite Support & Assistance 3
OR-2 Release of Information to the Public 2
EF-1 Activation and Operation of the Technical Support Center 3
EF-2 Activation of the Operational Support Center 2
EF-3 Activation and Operation of the Emergency Operations Facility 4
EF-4 Activation of t:1e MEML 5
EF-5 Emergency Equipment, Instruments & Supplies 4
EF-6 Operating Procedures For EARS 9845C Controlling Stations 2
EF-6S1 Transfer of EARAUT Control 1
EF-7 Activation of the Nuclear Data Communications Systems 1
EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 0
RB-1 Personnel Dosimetry 0
RB-2 Emergency Exposure Guides 1
RB-3
' Stable Iodine Thyroid Blocking 0
RB-4 Access to a Establishment of Controlled Areas Under Emergency 0
RB-5 Personnel Decontamination 0
RB-6 Area & Equipment Decontamination 1
RB-7 Emergency On-Site Radiological Environmental Monitoring 3
RB-8 Emergency Off-Site Radiological Environmental Monitoring 4
RB-9 Calculation of Release Rate & Integrated Release 2
RB-10 Protective Action Guidelines O
RB-11 Emergency Off-Site Dose Calculations 3
RB-12 Mid and High Range Plant Vent Radiation Monitors 1
RB-13 Improved In-Plant Air Sampling for Radioiodines O
RB-14 Core Damage Assessment Procedure 1
07/20/84 0502d/0005K J
IP@r5743 Pacific Gas and Electric Company NUMBER EP EF-4 0
m REVISION 5 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE M LE:
g ACTIVATION OF THE MOBILE ENVIRONMENTAL MONITORING LABORATORY IMPORTANT Yb APP 30VED.
SAFETY PLANTMANAh DATE SCOPE This procedure delineates the requirements and actions to be taken to activate the Mobile Environmental Monitoring Lab (MEML).
This procedure and changes thereto requires PSRC review.
GENERAL The MEML will be used to measure radiation levels in the environment at various offsite locations for use in offsite assessment activities.
The unit is equipped with an intrinsic germanium (ige) detector; a sodium iodide (Nal) detector; a multichannel analyzer; a Hewlett-Packard 9845C computer with mass storage discs; a high volume air sampler; one pressurized ion chamber; emergency instrumentation and equipment kits; thermoluminescent dosimeter (TLD) reader and TLD's; consnunications equipment for contacting the onsite Technical Support Center (TSC) and the Emergency Operations Facility (EOF); and its own electric generators. Figure I shows the MEML's floor plan.
The MEML is located and maintained at the PGandE San Luis Obispo Service Center, 4315 South Higuera Street, San Luis Obispo, California. The MEML is housed in its own garage across from the service center garage. The keys to the MEML are located in the ignition. A second set of keys is available from the Service Center Garage Key Rack.
The MEML garage also serves as the storage area for offsite monitoring team equipment and as a staging area for field monitoring activities.
It also serves as the office, shop, and staging area for the Normal offsite radiological monitoring program.
l 4
DC0070 IVIII l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP EF-4 REVISION 5 DATE 5/23/84 PAGE 2 0F 8.
m LE:
ACTIVATION OF THE MOBILE ENVIRONMENTAL MONITORING LABORATORY
- It is locked and protected with a burglar alarm system when unoccupied. Defeat keys for the burglar alarm are available from the Department of Engineering Research (DER) personnel normally assigned to the MEML Garage Operational Security, the Shift Foreman or the Che'nistry and Radiation Protection Key Box at Diablo Canyon Power Plant.
Access to a PGandE telephone system can be found in the division office area across from the MEML garage (see Figure 2). The doors into the division lunch room are keyed to accept the corporate "3A90909" key. Telephones are located in offices across from the kitchen.
INITI ATING CONDITIONS 1.
Emergency Conditions a.
The Site Emergency Coordinator declares that the plant is in an Alert, Site Emergency, or General Emergency status as defined in Emergency Procedure G-1 "Acc % nt Classification and Emergency Plan Activation " and initiates the emergency organization in accordance with Emergency Procedure G-2
" Establishment Of The Onsite Emergency Organization."
SUBSEQUENT ACTIONS 1.
The staging point for the field monitoring teams and storage area for the radiological emergency kits is the MEML garage located in the San Luis Obispo Service Center, the personnel dispatched to the MEML garage will generally consist of Chemistry and Radiation Protection Technicians (C&RP), the MEML Operators from PGandE Department of Engineering Research, and San Luis Obispo County Environmental Health Department Personnel.
f0TE: If the MEML garage is locked, personnel should not open the door without a burglar alam defeat key available.
The front door is the only access that has a 45 second, ).
time delay to pennit use of the defeat key (see Figure 2 The defeat key O available from the plant if the DER personnel are not available. The DER personnel will be called out as part of the call-out list in Emergency Procedure'EP G-2.
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ACTIVATION OF THE MOBILE ENVIRONMENTAL MONITORING LABORATORY 2.
a.
When PGandE personnel have reached the MEML garage, establish telephone contact with the Radiological Emergency Recovery Manager (RERM) at the Emergency Operations Facility (EOF)(seeAttachment1). If the MEML garage is locked and access cannot be obtained from the DER personnel assigned to the van, then use the telephone in the division office building (see Figure 2).
N)TE: If the RERM cannot be reached at the EOF, then contact the Emergency Radiological Advisor (ERA) at the onsite Technical Support Center (see Attachment 1).
b.
If the RERM or the ERA require innediate deployment of the MEML and/or the field monitoring teams, and access to the garage is still not available, inform the RERM/ ERA that access is not available and request the Cypner Pad Code that will open the door. Also request the ERA to dispatch an individual from the plant to reset the alann.
c.
Call DCPP security (see Attachment 1) to inform them the MEML garage will be entered, and that the alarm will be actuated.
1 N)TE:.When the alann is actuated a loud electronic warbler will sound locally.
3.
Activation of the MEML:
j a.
Switch the radiological monitoring equipment over from house power to the Onan electric power source by disconnecting the umbilical cord for the house power. For delineation of steps required for this operation, refer to the MEML Equipment Operations Manual. Disconnect all other shore leads (as per placard on steering wheel).
b.
Start the van and innediately drive van outside garage -
Close & Lock Garage Door.
K)TE: If van is kept in garage with engine or generators running the fire alann system will be actuated in a very short period of time.
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ACTIVATION OF THE MOBILE ENVIRONMENTAL
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MONITORING LABORATORY c.
Check the operability of the portable high pressure ion chambers (PIC), including their response to check source and battery levels.
d.
Start the two (2) Onan electric generators.
e.
Verify the operation and calibration of the multichannel analyzer (MCA) following the calibration procedure in the MEML Equipment Operations Manual.
f.
Establish verbal contact with the TSC and the EOF via the van's radio and the radio telephone systems.
I RADIOLOGICAL MONITORING EOUIPMENT OPERATING INSTRUCTIONS Detailed operating instructions for the radiological monitoring equipment is provided in the van as the MEML Equipment Operations Manual.
COMMUNICATIONS Radio communications includes two-way voice transmission via radio to the TSC, the EOF and field monitoring teams, and radio telephone to any location served by Pacific Telephone. The radio telephone is the preferred communication means for the van.
FIGURE 1.
Floor Plan of the Mobile Environmental Monitoring Laboratory 1.a. Left Side View of the Mobil' Environmental Monitoring Laboratory e
1.b. Right Side View of the Mobile Environmental Monitoring Laboratory 2.
Garage Layout and Phone Access ATTACHMENTS 1.
Phone Numbers 2.
Contamination Control for the Mobile Environmental Monitoring Laboratory 3.
Mobile Environmental Monitoring Laboratory Sample Log-in Sheet Form f 69-11533 5/84 (25)
SUPPORTING PROCEDURES
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RB-8 Emergency Offsite Radiological Environmental Monitoring Program DC0070 4VIII 6
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DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP EF-4 REVISION 5 DATE 5/23/84 PAGE 5 0F 8 ACTIVATION OF THE MOBILE E$VIRONMENTAL TITLE:
MONITORING LABORATORY i.
FIGURE 1 FLOOR PLAN OF THE MOBILE EWIlDIRDiTAL MONITORING LABORATORY I
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ACTIVATION OF THE MOBILE ENVIRONMENTAL LONITORING LABORATORY FIGURE 1.a.
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10/83 Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 TITLE: EMERGENCY FACILITY PHONE NUMBER 1.
ENERGENCY OPERATIONS FACILITY:
Call Operator Radiological Emergency Recovery Manager ask for or PT&T Radiological Monitor'ing Director or PT&T UDAC or PT&T i
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j Call Operator Emergency Radiological Advisor ask for or PT&T l
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DCPP SECURITY j
Security Shift Supervisor or PT&T Central Alarm System Secondary Alarm System l
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1/84 Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIA8LO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: CONTAMINATION CONTROL FOR THE MOBILE ENVIRONMENTAL MONITORING LA80RATORY (MEML)
!. Sample Handling - MEML Personnel A.
Securely affix a double layer cover on all appropriate work surfaces 3
(i.e., work surfaces used to prepare potentially contaminated i
samples for analysis).
3 8.
Gloves should be worn when handling potentially contaminated samples (e.g., air sampler filter heads and vegetation and soil samples).
C.
Perform smear surveys on the sample bags to detemine if the outsides of the sample bags are contaminated.
1.
If a sample bag is contaminated, place it in another j
non-contaminated sample bag, stored in the van.
2.
Use good contamination control and ALARA techniques throughout the sample analysis.
j D.
When purging iodine cartridges, avoid contamination by venting the.
j effluent directly to the outside of the lab. A purge vent is located over the sample handling bench and is so marked.
E.
Upon completion of sample analysis, store the samples in a large j
plastic bag. Label the bag.
l' II. Sample Delivery and Transfer - Offsite Monitoring Teams Personnel i
A.
Field monitoring team personnel should pass samples into the van through the sample transfer door located towards the rear of the van, on the passengers' side.
8.
If the sample transfer door is inoperable, the samples may be passed through the backdoor.
l 1.
If possible, field monitoring personnel should remain outside so as not to track contamination into the van.
2.
If field personnel must enter the van, a step-off area should
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Field monitoring personnel should frisk their hands, feet and any other potentially contaminated area, before entering the clean step-off area.
4.
Shoe covers and gloves should be available so that personnel may leave the van and enter contaminated areas, if necessary.
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Contaminated personnel should not enter the.MEML under any circumstances.
III. A.
When analysis is complete, and samples stored, carefully remove the covering from the work surface (s). Rubber gloves should be worn and care should be taken to ensure the containment of any contaminants E
present. Dispose of the covering, gloves, etc. in a labeled plastic N
bag.
8.
Upon completion of all MEML activities, perform smear surveys on the inside of the van to ensure that no contamination exists. If contamination is found to exist, decontaminate as appropriate.
C.
If the van was near the plume and the potential for contamination exists, perform smear surveys on the outside of the van. If contamination is found to exist, decontaminate as appropriate.
D.
When van is determined to be free of contamination, return to garage.
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PGwE DIABLO CANYON POWER PLANT 7,,,,,%7 PROCEDURE ON-THE-SPOT CHANGE eiessen.No. EP RB-5 n
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PERSONNEL DECONTAMINATION Tyse se ene,. @.mauamawT (erseas O 7:=aoaaav Ir ->; c.ir.ii o.i.
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%% CHEM AND RAD. PROTFETTON INSTRUCTIONS:
Complete Appropriate Columns 1.) PROCEDURE PAGE CHANGED ADD PAGE DELETE PAGE NEW PAGE Ntf'BER 8 of 1_1 2.) ATTACHMENTS Attachment Number (Include all pages with dates changed to date of this 0TSC)
- 2 cace 8 FORM 69-11510 nm aes,ensa Incoporate use of new survey forin.
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P RB-5 DATE 7/21/81 PAGE : 7 08' 11 Tms:
PERSONNEL DECONTAMINATION
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a.
Shoes
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- 1) If it is susoected that the contarinant is particu1 ate matter, masking tape may remova it. Pren the gunsny side of the tape to the area of the shoe that is contaminated. Remove and repeat until ro substantial reduction in radiation level is '
observed or until the shoe is froe of contamination.
- 2) If the contamination cannot be emved with tape, leather soles should be scraped with a wire b Jsh or emery paper until cle.an.
Keep dust and filings from flying into the air. 00 NOT USE WATER OR LIQUIDS ON LEATHER because the leather wTTI sweWup
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- 3) If contamination cannot be remcved with tape, rubber soles may be senabbed with decontamination soap. fD0 NOT USE ON LEATHER SOLESORUPPERS.) A wire or stiff bristDrush7oWd be used. l ipe off, rinse, dry and resurvey. Repeat if necessary.
- 4) Wire brushes should be washed with clean soapy water to prevent the spread of contamination.
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- 5) Shoes that cannot be decontaminated by'these methods should be co.fiscated, placed in a plastic bag, and labeled. Disposition of contaminated shoes is to be left to the discretion of the Emergency Radiological Advisor.
b.
Personal Clothing
- 1) Contaminated clothing will be confiscated, placed in a plastic bag and labeled. Disposition of all clothing will be left to l
the discretion of the, Emergency Radiological Advisor.
- 2) A body survey for skin contamination will be made.
- 3) Temporary clothing will be issued.
SUPPORTING PROCEDURES EP R-1, " Personnel Injury (Radiological Related) and/or Overexposure" EP RB-2, " Emergency Exposure Guides" DC0003 7
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NUMBER EP RB-5 DWGLO CANYON POWER PLANT UNrr NO(5)
RNSACN O
DATE l1' 7.Il d PAGE g OF i
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PERSONNEL DECONTAMINATION s e i
TABLES 1.
Decontamination Supplies to be Obtained from the Supply Room.
2.
Acceptable Surface Coritamination Levels.
ATTACHMENTS e
1 1.
Fors.36-9392. " Skin and Clothing Decontamination.#he-+"
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DIABLO CANYON POWER PLANT RADIATON AND CONTAMINATION SURVEY. FORM' samt r
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UlJITED STATES i,,g.
NUCLEAR REGULATORY COMMISSION
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Aagust 8, 1984 g
50-275/323 Diablo Canyon N
MEMORANDUM FOR:
Chief, Document Management Branch, TIDC FROM:
Director,' Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be mAde publici available.
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yV 1/Y J. M. Felton, Director Division of Rules and Recor s' H[
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Office of Administration l
Attachment:
As stated 1
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