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Public Version of Affidavit of Re Linnemann Re Intervenor Citizens Assoc for Sound Energy Contention 22 Concerning Svcs of Medical Personnel for Radiation Emergencies. W/Resumes,Notice of Appearance & Certificate of Svc
	ML20065G115
Person / Time
Site:	Comanche Peak
Issue date:	08/20/1982
From:	Linnemann R; RADIATION MANAGEMENT CORP. (RMC), TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20065G093	List: ML20065G102; ML20065G105; ML20065G110; ML20065G113; ML20065G115;
References
	NUDOCS 8210040037
	Download: ML20065G115 (21)
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---.ar UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ,

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of: )

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TEXAS UTILITIES GENERATING ) Do cke t Nos . 5 0-44 5 COMPANY, _e t _al . ) 50-446 -

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(Comanche Peak Steam Electric )

Station, Units 1 and 2) )

AFFIDAVIT OF ROGER E. LINNEMANN, M . D.

CONCERNING INTERVENORS' CONTENTION 22 ON EMERGENCY PLANNING My name is Roger E. Linnemann, M.D. My business address is 3508 Market Street, Philadelphia, Pennsylvania, 19104. A statement of my educational and professional qualifications is attached hereto as Attachment A. I am Vice-Chairman of Radiation Management Corporation ( RMC), which provides Texas Utilities Generating Company (TUGCO) with emergency medical assistance in the event of an accident at the Comanche Peak Steam Electric Station (CPSES). The purpose of my affidavit is to' discuss subparts (c), and (e) of Intervenor's Contention 22 on emergency p)anning, which read ,as follows :

c. There is no discussion of the arrangements for services of physicians and other medical personnel qualified to handle radiation emergencies and arrangements for the 8210040037 820921 PDR C

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transportation of injured or contaminated individuals beyond the site boundary.

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e. There is no provision for medical facilities in the immediate vicinity of the site, which includes Glen Rose. --

Contention 22.c relates to two aspects of emergency planning, viz., arrangements for medical services for radiation emergencies and arrangements for transportation of injured yut _

i contaminated individuals beyond the site boundary. Contention 22.e relates to the provisions for medical facilities near the site.

Sections 1.3.1.4 and 10.0 of the CPSES Emergency Plan

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A copy of the Plah~Ts ~ ~

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describe the medical support services.

j attached to the Af fidavit of Richard A. Jones that is being' filed s

simultaneously herewith.

Hood General Hospital in Granbury, Texas, located approximately sixteen road miles from CPSES, is the primary

facility for treatment of radiological injuries resulting from an l emergency at CPSES. TUGCO has obtained a Letter of Agreement from m

i Hood General Hospital to receive and treat injured persons who are contaminated with radioactive material or who have an overexpos ure requiring medical evaluation. A copy of the Letter of Agreement is included in the CPSES Emergency Plan at Section IS, Appendix H.

{ Backup medical services, suppo rt, and definitive care are provided l through a Letter of Agreement with the Radiation Management i

corporation and its i

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, , affiliation with a medical center for definitive care at Northwestern Memorial Hospital in Chicago. A copy of the Letter of Agreement between RMC and Northwestern Hospital is attached hereto as Attachment B. A copy of the Letter of Agreement between RMC and TUGCO is found at Appendix H to Section 15.0 of the CPSES Emergency Plan. Injured persons whose medical treatment is not complicated by radiological considerations may be sent to either Hood General Hospital or Marks English Hospital, which is approximately eight road miles distant, in Glen Rose, Texas.

(CPSES Emergency Plan, $$ 1.3.1.4, 10.0, and 15.0 Appendix H)

Hood General Hospital serves as the local support i hospital for contaminated victims, providing gross decon-tamination, life saving activities, and patient stabilization. In the event a victim requires more definitive evaluation and treatment, the individual may be sent to the Radiation Management j Corporation facilities at Northwestern Memorial Hospital in Capabilities at the Northwestern Memorial Hospital Chicago.

l include a fully equipped radiosurgery suite, reverse isolation units, facilities for white cell transfusion, bone marrow trans fusion, and chronosome analysis. (CPSES Emergency Plan $$

1.3.1.4, 10.0, 15.0 Appendix H)

Transportation of a radiologially injured patient to Chicago will be arranged by RMC with private surface and air transportation services. Appropriate protective measures (such as isolated transportation, if necessary, and attendance by technicians trained in transporting and handling radiologically

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i contaminated patients) will be instituted by RMC and TUGCO. w Additional support provided by RMC includes around-the-clock, seven-day-per-week availability of expert consultation and ' -" /

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services of a radiation emergency medical team consisting of a licensed physician experienced in radiation medicine, a certified health physicist, and technicians with portable instruments to respond to an accident victim at CPSES or Hood General Hospital as

.- requested by TUGCO. RMC will provide the services of its bicassay laboratory and whole body counting f acility if requested. RMC will also conduct a semi-annual review of plant and hospital -

procedures; provide annual training for plant, ambulance, and hospital personnel involved in the radiation emergency medical 4

program; preparation of a radiation ac'cident scenario,

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coordination of a medical emergency drill, and evaluation, reports. ,

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Additionally, RMC will conduct an annual seminar on canagement 'of'/ 7 radiation accidents for physicians and other medical persont3el.

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. (CPSES Emergency Plan { l . 3.1.4, 10.0, 15.0 Appendix H).

Under the county emergency operations plan, the Hood '

County Hospital Administrator is responsible' for coordinating i

- medical care and treatment for injured individuals (both t

contaminated and non-contaminated) with local medical facilities, establishing medical care and treatment centers if needed, maintaining medical records, establishing resupply requirements, providing emergency medical care to persons in shelters, and establishing triage centers if necessary. (Hood County Plan, }

VI(10)). This is detailed further in Annex F,Section V(J), the

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. . " Hood County Fixed Nuclear Facility Response Plan", a copy of which is attached to the Af fidavit of Richard A. Jones as k

Attachment B. In addition, specific procedures to be followed by the hospital / emergency medical group are provided in Section IV of the " Manual of Emergency Proceduros for Incidents Involving the 2

Comanche Peak Steam Electric Station" as an Appendix to the County Fixed Nuclear Facility Response Plan. These procedures include specific instructions to the Hospital Administrator and procedures to be followed in the event of an Unusual Event, an Alert, a Site Area Emergency, and a General Emergency at CPSES. The Somervell County-City of Glen Rose Emergency Operation Plan (Section VI(9)),

Fixed Nuclear Facility Response Plan ( Annex F,Section V(J)), and Manual of Emergency Procedures (Section IV) contain provisions fo r

p. hospital and medical personnel in Somervell County similar to those for Hood County. A copy of the Somervell County Plans and Procedures is attached to Mr. Jones Af fidavit as Attachment B.

TUGCO has obtained written agreements with the Glen Rose /Somervell County Volunteer Fire Department Ambulance Service b and the Hood General Hospital Ambulance Service to provide back-up assistance to TUGCO for transporting injured and contaminated vict ims for medical assistance. A copy of those agreements are

included in the CPSEh Emergency Plan at Section 15.0 Appendix H.

I f The CPSES Plan is being submitted as Attachment A to Mr. Jones Affidavit. Hood General Hospital Ambulance Service can provide one ambulance with an emergency medical technician and paramedic and Somervell County can provide one ambulance. A TUGCO ambulance c

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. . is available at CPSES to transport injured personnel, who may also be radiologically contaminated, to the appropriate medical facility. RMC will train and exercise ambulance service personnel in the transportation and handling of radiologically injured patients. CPSES Emergency Plan $ 15.0 Appendix H. CPSES Emergency Plan Procedure, EP P-3 0 8 , " Transporting of Contaminated Injured Personnel" describes the specific requirements for transporting injured and contaminated victims. (CPSES Emergency Plan $$ .

1.3.1.3, 10.2, 15.0 Appendix H).

Contention 22.e raises concern about the adequacy of medical facilities in the immediate vicinity of the site, including the City of Glen Rose. As previously stated, arrangements have been made and agreements obtained with the Hood County General Hospital and Radiation Management Corporation to provide medical care for contaminated, injured personnel from CPSES. (CPSES Emergency Plan $ 15.0 Appendix H). These are the prima ry facilities for care of radiologically contaminated persons i from CPSES. Injured individuals who are not radiologically contaminated may receive care at the Marks English Hospital in Glen Rose and contaminated individuals, once decontaminated, could I

l be transferred to Marks English Hospital for treatment of non-l .

radiological injuries. (CPSES Emergency Plan $$ 1.3.1.4, 10.1, 15.0 Appendix H).

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j In summary, arrangements for transporting injured or i

j contaminated individuals and for qualified medical services to handle radiation emergencies are adequate and capable of being i implemented.

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Roger E. Linnenann, M.D.

4 STATE OF PENNSYLVANIA 1 COUNTY OF I.' ' 'l 9 .r2:'.0, -

Subscribed to and sworn ' ~

be fore me, this day of August, 1982.

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); Notary Public j 8y ComQgggjcpires:

4 ; Notary Public. Phila.. Phifa Co./ Commission Expires Maren 23, '9a5 l s 1 l 1 1 I d 4 3 1 4 L -

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ATTACHMENT A I l l CURRICULUM VITAE ROGER E. LINNEMANN, M.'D. Vice Chairman Radiation Management Corporation i i k O I i I, k

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SUMMARY

EDUCATION: My education is in medicine and science. I am a graduate of the University of Minnesota Medical School, with an internship and residency in radiology at Walter Reed Army Hospital, Washington, D.C. I PROFESSIONAL LIFE My professional life has been devoted to the field of ionizing radiation with special interest in the evaluation and treatment of radiation injuries and radiation health and safety. My research activities include the use of protective agents against radiation injury and the use of radioactive isotopes in the evaluation of renal disease. I spent twelve - .- years in the U.S. Army Medical Corps in clinical medicine, research and command operational activities concerned with the organization of medical facilities on a nuclear battlefield. I have academic and teaching appoint-ments at the University of Pennsylvania School of Medicine and the Northwestern University Medical School. My bibliography includes over 20 articles on radiation. 1 MANAGEMENT: My management experience comes from the organization and develop-ment of Radiation Management Corporation (RMC) , a business corporation incorporated in the State of Pennsylvania in 1969. RMC provides an emergency

medical response capability for nuclear facilities in twelve states, as well as routine consulting and laboratory services in radiation health and safety, i waste disposal, radiation and non-radiation environmental problems. As Chief Executive Officer I am responsible for the total operation, development and planning of RMC. Presently RMC has sales over $6 millien, employs 160 people and has seven offices throughout the United States.

SPECIAL INTERESTS: My personal interest has always been in foreign activities. { l While in the U.S. Army, I lived in Germany for seven years. I was a U.S. I delegate to NATO Medical and Radiation Committees.- I taught a seminar in i German at the University of Freiburg in 1967. I studied the Russian language for three years. On numerous occasions I was asked to participate in l conferences on radiation at the International Atomic Energy Agency in Vienna. Since I have been with Radiation Management Corporation I have been invited to numerous countries.(Ge: winy, Sweden, Spain, Korea, Japan) to conduct l seminars and consult on radiation health matters. t P I l f i

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                               .      -         Vice Ch=4 ==n Radiation Management Corporation 3508 Market Street University City Science Center Philadelphia, PA 19104                                                                 - -

(215)243-2950 . EDUCATION

University of Minnesota, Minneapolis, MN; B.A. (Cum Iaude) 1952 University of !dinnesota, Minneapolis, MN; B'.S., M.D. 1956 Walter Reed Army Hospital, Washington, D.C.; INTERNSHIP 1956-1957 Walter Reed Arx:,r E*ospital, Washington, D.C.; RESIDENCY (Radiology) 1962-1965 e** ... Certified by American Board of Radiology 1964 Certified by American Board of Nuclear Medicine 1972 Licensed to practice Medicine in 1) Commonwealth of Pennsylvania; 2) Illinois; and 3) Minnesota e **... Sandia Base, New Mexico; Nuclear Weapons Orientation Course 1961 W Walter Reed Army Institute of Research, Washington, D.C.; Medical Aspects of Nuclear Warfare 1962 US Department of Agriculture Graduate School (Evening), Washington, D.C. Russian Language 1963-1965 - PROFESSIONAL EXPERIENCE L 1981-present Vice Chairman and Chief Medical Officer, Radiation Management Corporation . 1969-1981 President / Chief Executive Officer, Radiation Management Corporation 1974-present Clinical Associate Professor of Radiology, University of Pennsylvania School of Medicine 1977-present Visiting Associate Professor, Clinical Radiology, Northwestern University Medical School 1969-1974 Assistant Professor, Clinical Radiology, University of Pennsylvania School of Medicine , 1 1968-1969 Nuclear Medicine Consultant, Philadelphia Electric Ccepany

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           ' '                 PROFESSIONAL EXPERIENCE (Continued) l.

i i Assistant Professor, Radiology, University of Minnesota Jan-Aug 1968 School of Medicine ' investigated use of isotopes in kidney function evaluation) . 1957-1968 Employed by United States Ar:ny .. . . 1965 1968: rnamanding Officer, Nuclear Medicine Research Detachment, ; i Europe; Radiological Health Consultant, US Army-Europe. j (responsible for plans, procedures and training of military ( j hospitals and personnel in the evaluation, evacuation and i treatment of radiation casualties. In January, 1966 sent to Palomaris, Spain for evalua'; ion of niedical and environmental I a.pects of the mid-air collision involving nuclear weapons)

               '1961-1962:      Research Associate, Department of Radiobiology, Walter Reed

] Army Institute of Research, Washington, D.C. (investigated use of anti-radiation drugs in treatment of cancer) 1957-1961: General Medical Officer, Europe I Languages: German, Russian ] l h PROFESSICNAL APPOINTMENTS 1 i 1979-present Health Physics Society Standards Committee 1978-present General Dynamics Electric Boat Division Radiological Health Consultant 1978-present Edison Electric Institute Utility Radiation Standards Group

)        1973-present           University g Pennsylvania Radiation Safety Cecimittee
;        1973-present           The Atomic Industrial Forum, Inc. Public Affairs & Information enmmittee                                  ,

1970-present The American Nuclear Society Subcommittee for Writing Emergency

-                                Procedures Standards I

j 1969 & 1975 Atomic Energy Commission ad hoc Ccmmittee on Medical Aspects of Radiation Accidents , 1966-present American College of Radiology .... l 1969-present Commission on Radiologic Units, Standhrds and Protection j 1969-present Committee on Radiation Exposure of Women ] 1969-present Committee on Radiological Aspects of Disaster Planning 4 1967-1978 International Affairs Committee 4 1 1965-1968 U.S. Delegate to NATO Radiation Protection Committee & Padical j Aspects of Nuc 5ar Warfare Committee 4 ( mueen -- 1, s - n--mm.mu,, m,vm , y _

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                                                                                                                                  .mmr-PROFESSIONAL APPOINTMENTS (Continued) 1971-present                Department of Defense & Environmental Protection Agency Medical Liaison Officer's Network (MLON)-State of Pennsylvania Representative                                           .

P PROFESSIONAL MEMBERSHIPS American College of Radiology American Public Health Association American Medical Association i Society of Nuclear Medicine i Philadelphia Roentgen Ray Society Pennsylvania Medical Society

College of Physicians of Philadelphia Radiological' Society of North America, Inc.

American Institute of Physicists /American Association of Physicists in Medicine American College of Nuclear Physicians American Council on Germany Union League of Philadelphia l AWARDS & HONORS l ._ _ _ 1978 Association of Medicine & Security, Madrid, Spain (Honorary Me=ber) l 1968 University of, Minnesota Radiological Research Scholar , (National Research Council) 1968 United States Army Legion of Merit ! PRESENTATIONS

1980 Korea Women's Association (Seoul, Korea) l presented paper, " Energy: The Basis for Health in Developing l and Developed Countries", at International Sy=posium on the Expulsion of Environmental Pollution .

1980 Korean Association for Radiation Protection (Seoul, Korea) ! presented seminar on emergency management of radiation injuries 1980 Ministry of Health (Madrid, Spain) l presented paper, " Definitive Treatment of Radiation Injuries",

at First Seminar on Assistance to Those Wounded by Radioactive Elements and Ionizing Radiations i,

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m l u ' PRESENTATIONS (Continued) . . l , 1979 Reinisch-Westfalisches Elekrizitatswerk (Essen, Germany) presented paper, " Energy: The Basis for Health in Developing and Developed Co.a tries", at The Seventh Energy Workshop I 1978 The Swedish State Power Board (Vallingby, Sweden) presented seminar, " Management and Treatment of Radiation

                            .                        Injuries", and conducted radiation emergency medical exercise at the Ringhauls Nuclear Power Plant l                       1978                          Deutsche Gesellschaft fur Wiederauf arbeitung (Hannover, Ger:n ny) appeared before the Prime Minister and Parliament of l

Iower Saxony as an International expert to testify on the l

1. safety of a reprocessing. plant at Gorleben, Germany i 1978 International Atomic Energy Agency (Vienna, Austria) presentation at Symposium on Late Effects of Ionizing Radiation 1978 Associacion de Medicina y Seguridad en el Trabajo de Unesa para Q Industria Electrica (Madrid, Spain) presented one-day seminar entitled, " Primary Management of Radiation Injury" l 1977 International Atomic Energy Agency (Vienna, Austria) __ presented paper, " Emergency Medical Assistance Programs for Nuclear Power Reactors", at Symposium on Handling of Radiation Accidents 1967 University _of Freiburg Institute of Radiobiology (Freiburg, l i Germany); presented seminar on diagnosis and treatment of radiation injuries

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a PROFESSIONAL TESTIMONY _ in progress Southern California Edison Company Emergency Planning Hearings for the San Onofre Nuclear Generating Station in progress Florida Power & Light Company Turkey Point Steam Generator Repair Hearings in progress Pennsylvania Power & Light Company Susquehanna Steam Electric Station Operating License Hearings ( in progress John Benek v. Pennsylvania Power Company et al. #199 of 1977 Eminent Demain 1979 Gorleben Nuclear Fuels Reprocessing Plant Hearings before the Prime Minister and Parliament of Lower Saxony, Hannover, Germany 1979 Florida Power & Light Company Turkey Point Nuclear Station Operating License Hearings 1971 Long Island Lighting Company Shoreham Nuclear Power _ Station Operating License Hearings 1970 Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Operating License Hearings 1970 Northeast Utilities Service Company Millstone Nuclear Power Station Operating License Hearings 0 l i i 4 e l i t i E P

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PUBIJCATICES

1. Linnmann, Ibger E. " Berlin: 2 e Young-Old City". Senior Citizen (Septarber 1961) -

2. Linnenann, Ibger E. "this Way to Berlin". W e American Benedictine Review:M, No. 4 (W21963)

3. Linner: ann, Ibger E. "2e Acute Radiation Syndure and its Irpact cm the Chain of Evacuaticn". Medical Bulletin, U.S. Ar:w Euroce:---22, No. 12

                                                                                  ^      ^

(

Dearter 1965) ,

l

4. Linnemann, Ibger E. and Ibbert T. Wangemann. "WJ< al Support of Nuclear Weapcns Accidents". Medical _ Bulletin, U.S. An:?/ Eurooe (Noveier 1967)

5. Linnemann, Roger E. and O. Messerschmidt. "Erholto:gsvorgaenge bef Grosetieren ncoh Gan:koerperbestrahl:o1g", :dem 6_, Jahrbuch ven der vereinigung Duetscher Strahlenschut-M a (1968)

6. Linnerann, Ibger E. "Ocmrend Radiation Guidance". Military Medicine: 33, pp. 771-716 (Septer:ber 1968)

7. Icken, Merle K. , Linnemann, Ibgr E.. and George S. Kush. "Evaluaticn of Renal Function Using a Scintillaticn Camera and Ccrputer". Radiolcef: 93, -

No. 1, pp. 85-94 (July 1969)

8. Linnemann, Ibger E., Icken, Merle K. and Colin Markland. "Ccrputerized Ccrpart:: ental Renograms to Study Kidney Functien". Journal of_ Urology: 103, pp. 533-537 (May 1970)

9. Linnerrann, Ibger E. and J.W. Miessen. " Regional Approach to the Management of PaMeicn Accidents". Journal of the Arerican Public Health Associaticn:

61, 1 No. 6, pp.1229-1235 (June 1971)"

10. Linnemann, Ibger E. and Robert H. Holmes. " Nuclear Accidents and h eir Management". Emergency Mir-al Care, pp. 281-292, Spitzer, Stanley and Wilbur W. Oaks (eds.) New York: Brune ard Stratton, Inc. (1971)

11. Linnemann, Roger E. , Rasmussen, N.C. and F.K. Pittran. Nuclear Ener:rf:

l Issues and Answers. Atcr:ic Industrial Forum, Inc. in cooperaticn with Pennsylvania Power & Light Ccrpany (April 1973) l 12. Linnemann, Ibger E. " Accentuate the Positive". Trial: _10_, No. 4, p. 13 . (July /AtxJust 1974) -

13. Linnemann, Ibger E. " Accentuate the Positive". Congressional Recrd: 109, pp. 4964-4967. Washingt=n, D.C." thited States of America PrMMgs and Debates of the 93rd Cbngress, Second Sessicn (July 23, 1974)

14. Linnemann, Ibger E. and J.W. Miessen. Editorial, "In Defense of Radiaticn and re-11 <t" . We New York Times (May 23, 1974)

(Centinued)

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m. - __ me m-- _- . :- s i reger E. Linnemann - Ptblications Nuclear Radiation and Health. Springville, NY

15. Linnemann, Ibger E.

Nuclear Fuel Services, Inc. (Septeter 23, 1974) .

16. Lirmemann, Ibger E. Editorial, "In Defense of Nuclear Power Plants",

he Philadelphia Incuirer, p. llA (March 6,1975)

17. Linnemann, Ibger E. " Nuclear Power Plants Pcse Minimal Health Risks",

Perspective. News Bureau of the University of Pennsylvania, Philadelphia, PA (February 1975) .

18. Lirmerann, Ibger E. " M ical Aspects of Power Generation". Impulse.

l Massachusetts: Electrical Comcil of New England (June 1975) , 19. Linnerann, Roger E. " Bugs in the Nuclear Fuel Cycle". Spectrun, p. 59, i Gadi Kaplan (ed.) Piscataway, N7: h e Institute of Electrical and . Electrcnic Engineers, Inc. (Septanber 1975)

20. Linne ann, Ibger E. and Fred A. Mettler, Jr. "Dnergency Wical Assistance Programs for Nuclear Power Reactors". Internaticnal Atcrnic Energy Agency Syqcsiun on the Handling of Radiaticn Accidents, IAEA-S+ 215/22, Vienna Austria (1977); 21. Lirmenann, Ibger E. "Why AIARA?" Transacticns of 1979 American hix: lear Society Conference, Atlanta, GA (June 3-7, 1979), Vol. 32, T7d5 AO 32 1 832 i ISSN 0003-018x (1979) t g 22. Linnemann, Ibger E., Hackbarth, C.J. and Ray Crardall . "B e Contaminated
and Injured Patient". ProcaMings of 'IWenty-fourth Annual Meeting of the Health Physics Society, July 9-13,1979 (Philadelphia, PA) s f 23. Lirmemann, Ibger E. "B e tree Mile Island Incident in 1979: % e Utility

! Respcnse". Se Medical Basis for Radiation Accident Preciths, K.F. Hubner and S.A. Fry (eds.) , Elsevier/ North-Holland, pp. 501-509 (1980) i 24. Linnemann, Ibger E. " Initial Management of Radiaticn Injuries". Journal of l Radiatio _n_ Prctection, 5_, No.1, pp.11-25 (Deceter.1980) 1 1

25. Linnenann, Ibger E. " Facilities for Handling the Ccntatainated Patient".

! Radiation Accident Precaredness: W ical and Manscerial Ascects, Science-Dru-Media Ccr m : New York (1980) , ! 26. Linnenann, Ibger E. "A Systans Approach to the Initial Management of j Radiation Injuries". Systems Approach to Dne.w Medical Care, Appleten-l . Century-Crofts: New York (1980) W i ( 27. Linnenann, Roger E., Stephen M. Khn and Frazier L. Bronscn. "2 ree Mile ( Island: M ical and Public Health Aspects of a Radiation M dant". ) Journal of Radiaticn Protecticn, 6_, No.1, pp. 45-52 (Och 1981) s k a 4 6

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Prentice Women's Institute A consolidation of Hospital and of

               . Chicago Wesley and Passavant                                           Maternity Center    Psychiatry Memorial Hospitals i
 !               Superior Street and Fairbanks Court
 !               Chicago, Illinois 6061I                                                                 ..

312 649 2000 l May 20, 1982 1' - Roger E. Linnemann, M.D. President Radiation Management Corporation Suite 400 _ 3C3 Market Street i Philadelphia, PA 19104

Dear Dr. Linnemamann:

Northwestern Me=orial Hospital agrees to accept referrals for the i evaluation and treatment of radiation injuries from Radiation I Management Corporation (RMC) and/or the nuclear power plants currently associated with RMC's E=ergency Medical Assistance Program (list attached) . The clinical management and decisions regarding the need for hospitalization and/or other treatment shall be under the direction of W. Harrison Mehn, M.D. Northwestern Memorial Hospital has and will maintain the clinical and medical capability to treat persons injured as a result of overexposure to ionizing radiation, which includes but is not limited to controlled patient environment, bone marrow transplant, white cell transfusions, 4 karyotyping and a radiosurgery decontamination unit. Northwestern Memorial l Hospital agrees to make these special facilities and equipment available

for radiation injury victims referred to Northwestern Memorial Hospital > by RMC and/or its participants in their E=ergency Medical Assistance ! Program. Northwestern Me=orial Hospital agrees to continue the inte-

 !                gration of these facilities into its regular teaching and hospital care i

program. .I j Further, Northwestern Memorial Hospital will maintain a Radiation Emergency Coordinating Committee and hold an annual meeting to review accident } cases and update knowledge regarding radiation injuries and procedures. g Northwestern Memorial Hospital will hold an annual training and drill for i its staff in the care of the radioactively contaminated patient and~

 '                evaluation of overexposure to radiation injuries.

It is understood that RMC will assist Northwestern Memorial Hospital in l maintaining its capabilities to handle radiation injuries and provide i consultation and laboratory radiation injuries. This agreement shall remain in effect until terminated by sixty days notice 3 given by Northwestern Memorial Hospital or Radiation Management Corporation. 1 incerely, I s i u V al u ? GLH/b1 Geo ge L. Heidkamp ) Executive Vice President ! cc: W. Harrison Mehn, M.D. A member of the McGaw Medical Center of Northwestern Univeruty f

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l T i I l . I i EMERGENCY MEDICAL ASSISTANCE PROGRAM CLIENTS Baltimore cas & Electric Company Cleveland Electric Illuminating Company *

Commonwealth Edison Company (6 sites) i Detroit Edison Company *.

/ General Public Utilities (2 sites) { Georgia Power Company (2 sites) Illinois Power Company Indiana & Michigan Electric Co=pany Long Island Lighting Company i Mississippi Power & Light Company Niagara Mohawk Power Corporation Northeast Utilities Service Company (2 sites) Pennsylvania Power & Light Company Philadelphia Electric Company (2 sites) Public Service Electric & Cas Company (2 sites) Public Service Company of Indiana

Rochester Cas & Electric Corporation Southern California Edison Company Texas Utilities Service Company
Union Electric Company *
denotes utilities with reactors in the construction phase sho have indicated "

participation as the reactors are activated 1 l i

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I j UNITED STATES OF AMERICA j ' l NUCLEAR REGULATORY COMMISSION

  !                              BEFORE THE ATOMIC SAFETY AND LICENSING BOARD                     --

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  !.           In the Matter of:                                     )                                                 ;

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                                                                     )
 )             TEXAS UTILITIES GENERATING                            )  Do cke t Nos . 50-445 ~
                                                                                                         ~         ~~)

COMPANY ) 50-446 I ) i (Comanche Peak Steam Electric ) j Station, Units 1 and 2) ) l l 1 i NOTICE OF APPEARANCE ' 1 Notice is hereby given that the undersigned attorney herewith enters an appearance in the captioned matter. In j accordance with 10 C.F.R. $ 2.713, the following information is i provided:

))l Name                       -

Jeb Curtis Sanford l Address - Debevoise & Liberman 1200 Seventeenth Street, N.W.

 )                                                                     Washington, D.C.             20036 Telephone                  -

(202) 857-9800 U

]                                       Admission                  -

Supreme Court of Texas a b lI h. Je'd C . SanforU i

Dated at Washington, District of Columbia this 23rd day of al l August, 1982. -

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     .--+,~n-_n-.                              --          -

_--n w .a 4 t, ^ UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of: ) - - TEXAS UTILITIES GENERATING ) Docket Nos. 50-445 COMPANY, et al.

                               --                        )                50-446
                                                         )

(Comanche Peak Steam Electric ) Station, Units 1 and 2) ) CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing " Applicants' Motion for Summary Disposition of Intervenor's Contention 22 Regarding Emergency Planning, " Applicants' Statement of Material Facts Not Genuinely in Issue", " Affidavit of Richard A. Jones Concerning Intervenor's Contention 22 on Emergency Planning",

                " Affidavit of Bobby T. Lancaster Concerning Intervenor's Contention 22 on Emergency Planning", " Af fidavit of Roger E. Linnemann, M.D.

Concerning Intervenors' Contention 22 on Emergency Planning", and

                " Notice of Appearance", in the above-captioned matter were served upon the following persons by hand delivery (*) or by overnight express (+) or by deposit in the United States Mail, first class postage prepaid, this 23rd day of August, 1982:

Marshall E. Miller, Esq. Chairman, Atomic Safety and Chairman, Atomic Safety and Licensing Board Panel Licensing Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555

              ~
                +Dr. Kenneth A. McCollom                      *Lucinda Minton, Esq.

Dean, Division of Engineering Atomic Safety & Licensing Architecture and Technology Board Oklahoma State University U.S. Nuclear Regulatory Stillwater, Oklahoma 74074 Commission Washington, D.C. 20555

                *Dr. Richard Cole, Member

Marjorie Ulman Rothschild, Esq.

Atomic Safety and Licensing Office of the Executive l Board Legal Director l' U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 m w-ae- m m . - -. - .- - n m - -me -=

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b b Chairman, Atomic Safety and David J. Preister, Esq f{ Assistant Attorney General G Licensing Appeal Panel U.S. Nuclear Regulatory Environmental Protection j Division u Commission ,l! Washington, D.C. 20555 P.O. Box 12548 Capitol Station [j Austin, Texas 78711 ,,

                    *Mr. Scott W. Stucky                                       +Mrs. Juanita Ellis            f il.

Docketing & Service Branch President, CASE U.S. Nuclear Regulatory 1426 South Polk Street f5 Commission Dallas, Texas 75224 Washington, D.C. 20555 [ h ti

                                                                                                                $,o e                                                                      E Jeb C. San 1%td
                                       /                                                                        j
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j I f i s n cc: Ec)ime r C . Schmidt ! Shencer

C. Relyea, Esq. t

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ATTACHMENT A COMANCHE PEAK f' STEAM ELECTRIC STATION l I iP (/h A. % f Y d b (D //\/g CC

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', c EMERGENCY PLAN

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l (,sEi COMANCHE PEAK STEAM ELECTRIC STATION EMERGENCY PLAN (CPSES/EP)

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                                           .                     Approved:          .        .
                                                                           % nager, &lgt Operations Date:          $ l3 f L

Revision 3 0 .

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k CPSES/EP TABLE OF CONTENTS Section Title g , l Preface 1 j 1.0 Organization 1-1 1.1 Normal Operating Organization 1-1

 ;           1.2          Onsite Emergency Organization                 1-1 l

1.2.1 Emergency Organization - 1-2 Responsibilities and Authorities

1.2.2 Manpower Needs for Emergency Condititns 1-16 l

l 1.2.3 Corporate Support 1-16 i j 1.3 Emergency Response Support 1-19 1.3.1 Local Agencies 1-20 1.3.2 State Agencies 1-21 1.3.3 Federal Agencies 1-22

[ 1.3.4 Private Agencies 1-24 I f 2.0 Emergency Classification System 2-1 } l 2.1 Emergency Action Levels 2-1 2.1.1 Notification of Unusual Event 2-1 2.1.2 Alert 2-8

2.1.3 Site Area Emergency 2-14 7

{ 2.1.4 Geheral Emergency 2-21 l 3.0 Notification Methods and Procedures 3-1 1 i r

l n t r E REVISION 3 MAY 21,1982

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TABLE OF CONTENTS Section Title . Pg . 3.1 Notification Messages 3-1 3.1.1 Initial Notification Messages 3-1 I l 3.1.2 Followup Emergency Messages 3-2 4.0 Emergency Communications 4-1 i 1 4.1 System Description 4-1 4.1.1 Public Address System 4-2 4.1.2 Intraplant Telephone System 4-2 j 4.1.3 Intraplant Sound-Powered Telephone 4-3 System i ! 4.1.4 Intraplant Portable Radio Transmitter 4-4 j Receiver System 4

4.1.5 Public Telephone System 4-4 i

l 4.1.6 Two-way Radio Transmitter - Receiver 4-4 System (Plant-to-Offsite) $ 4.1.7 Direct Telephone Line to the System 4-5 Dispatcher } 9 4.1.8 Emergency Evacuation Alarm System 4-5 ' 4.2 Emergency Notification System 4-5

4.3 Health Physics Network 4-5 i 4.4 Facsimile Communications 4-6 l .

l 5.0 Public Education and Information 5-1 l l 11 1 , K% \ Q) i REVISION 3 MAY 21,1982 1

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CPSES/EP 1 TABLE OF CONTENTS Section Title h 6.0 Emergency Facilities and Equipment 6-1 6.1 Technical Support Center 6-1 j 6.2 Operational Support Center 6-2 4 6.3 Emergency Operations Facility 6-2 6.4 State and Local Emergency Operations 6-3 . Centers 6.5 Emergency Aid Facilities 6-4 6.6 Emergency Equipment and Supplies 6-4 6.6.1 Safety Parameter Display System 6-5 6.6.2 Emergency Response Facility Computer 6-7 System 6.6.3 Radiation Monitoring System , 6-7 6.6.4 Health Physics Instrumentation 6-9 6.6.5 Meteorological Measurements Program 6-9 6.6.6 Seismic Monitoring 6-12 6.6.7 Hydrological Monitoring 6-15 4 6.6.8 Process Monitor Instrumentation 6-15 6.6.9 Fire Detection Instrumentation 6-15 6.6.10 Post Accident Sampling System 6-16 6.6.11 Offsite Radiological Monitoring System 6-17 7.0 Accident Assessment 7-1 111 t O REVISION 3 MAY 21,1982 Em___me, m - . . - - _ , . , _ _ m _. _ , - -- : - - - - - - - - - -

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Ny TABLE OF CONTENTS f j Section Title _ g 7.1 Control Room Assessment of Radiological 7-1 Conditions 7.2 Manual Assessment of Radiological 7-1 Conditions 7.3 Onsite and Offsite Radiological 7-2 Conditions 7.3.1 Onsite Radiological Assessment 7-3 l 7.3.2 Offsite Radiological Assessment 7-3 I 8.0 Protective Response 8-1 j 8.1 Onsite Protective Actions 8-1

 .               8.1.1          Evacuation                                  8-1 1

5 i 8.1.2 Personnel Evacuated from the Site 8-2 i x 8.1.3 Individual Protective Actions 8-2 ) ) 8.1.4 Personnel Accountability 8-3 8.1.5 Personnel Monitoring 8-3 l i 4 8.1.6 Emergency Response Time 8-3 1 4 8.1.7 Control of Public Access 8-3 s

i 8.2 Offsite Protective Actions 8-4 1

8.2.1 Emergency Planning Zones 8-4 j 9.0 Radiological Exposure Control 9-1 9.1 Emergency Exposure Criteria 9-1 i iv ( 2 I (c3' r 1 REVISf0N 3 J MAY 21,1982 s

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h. TABLE OF CONTENTS

    'u Section                         Title Pm 9.2             contamination Control                                    9-3 9.3             Decontamination                                          9-3 9.4             Radioactive Waste                                        9-4 10.0            Medical and Public Health Support                        10-1 10.1            Medical Treatment                                        10-1 10.2            Medical Transportaiton                                   10-2 10.3            First Aid                                                10-2 11.0            Recovery and Reentry                                     11-1 11.1            Recovery Organization                                    11-2 11.1.1          Recovery Organization - Job Functions                    11-3 12.0            Exercises and Drills                                     12-1 12.1            Exercises                                                12-1 12.2            Drills                                                   12-2 4

12.2.1 Communications Drills 12-2 12.2.2 Fire Drills 12-2 12.2.3 Emegency Medical Drills 12-2 i 12.2.4 Radiological Monitoring Drills 12-3 i 12.2.5 Health Physics Drills 12-3

12.2.6 Repair and Damage Control 12-3 v

I REVISION 3 MAY 21,1982 iz_ _r __ mw - - mew mm-" ~ "~ ^ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ' o C"

I l l CPSES/EP l- '(.}^) TABLE OF CONTENTS Section Title _Pa p,e l 12.3 Scenarios 12-3 13.0 Radiological Emergency Response - 13-1 Training -

,                  13.1                     Emergency Coordinator Training             13-1 l

13.2 Emergency Monitoring Training 13-1 13.3 First Aid Training 13-1 13.4 Fire Control 13-1 13.5 Repair and Damage Control 13-2 13.6 Offsite Groups 13-2 f 13.7 Offsite Medical Personnel 13-2 l i 13.8 Emergency Communications Personnel 13-2 t l 't - ? Emergency Organization Personnel 13-2 13.10 Emergency Planning Personnel 13-3 ! 14.0 Responsibility for the Planning Effort: 14-1 } Developmer.t, Periodic Review and 3 Distribution of the Emergency Plan 15.0 Appendices 15-1 2 1 1 - 1 vi I p @ i i i REVISION 3 ) MAY 21,1982 (; ,. ,;;5 ; - - . . . s e =. ' ~ <x: nw -' *~ ~ ~ " ~ ~ ' ~ ~ ~ ~~~ T'~~"~

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CPSES/EP LIST OF TABLES 5

Table Title g

1.1 Staffing Requirements for EOS*

Emergencies 1.2 Craded Emergency Organization Response EOS ! 2.1 Notification of Unusual Event 2-3 i j 2.2 Initiating Conditions: Notification 2-4 of Unusual Event 2.3 Alert 2-9 . 2.4 Initiating Conditions: Alert 2-10 2.5 Site Area Emergency 2-15 2.6 Initiating Conditions: Site Area 2-17 Emergency , 2.7 General Emergency 2-22 I 2.8 Initiating Conditions: General 2-24 Emergency 4.1 Emergency Communication Responsibilities EOS

6.1 Area Radiation Monitoring System EOS Parameters 6.2 Process Radiation Monitoring System EOS Parameters s

6.3 Health Physics Laboratory Equipment EOS f 6.4 Portable Health Physics Equipment EOS 6.5 Meteorological Instrumentation 6-11 6.6 Rea'c tor Trip System Instrumentation EOS

            *EOS - End of the Section vii b

REVISION 3 MAY 21,1982 e ,

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CPSES/EP LIST OF TABLES L Table Title g 6.7 Control Board Indicators EOS 6.8 Control Room Indicators EOS 11.1 Decision-Making Process for Event EOS Close-out or Transition to the Recovery Phase LIST OF FIGURES Figure Title , Pm 1.1 Function Interfaces EOS 1.2 CPSES Organization Chart EOS 1.3 TUGCo Nuclear Organization Chart EOS 1.4 Emergency Organization EOS 4.1 Communications Interfaces EOS 6.1 Integrated ERF Computer System EOS 6.2 Block Diagram Radiation Monitoring EOS System 6.3 Seismic Instrumentation Schematic EOS Diagram 6.4 Tabulation of Fire Hazards EOS 6.5 Environmental Monitoring Locations EOS

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                    ,                           LIST OF FIGURES
      ;.. - s, l   -.:'y Figure                            Title                       .

M ,, I 9.1 Decontamination and First Aid EOS Facilities in the Plant I 9.2 Emergency Operations Decontamination and EOS

  !                                       First Aid Facilities in the Nuclear I

Operations Support Facility 11.1 Recovery Organization EOS l -l i I L f - s ix i A

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[] CPSES/EP EP/FSAR TABLE AND FIGURE CROSS REFERENCE The following Energency Plan Tables and Figures are subj ect to change. Refer to the appropriate Table or Figure in the CPSES Final Safety Analysis Report if more detail is required. EP_ FSAR Table 6.1 (6 Sheets) Table 12.3-8 (6 Sheets) Table 6.2 (4 Sheets) Table 11.5-1 (4 Sheets) Table 6.3 (1 Sheet) Table 12.5-1 (1 Sheet) Table 6.4 (1 Sheet) Table 12.5-2 (2 Shee.ts) Table 6.6 (1 Sheet) Table 7.2-3 (3 Sheets) Table 6.7 (9 Sheets) Table 7.5-1 (9 Sheets) Table 6.8 (10 Sheets) Table 7.5-2 (13 Sheets) Figure 6.1 Figure II.A.1.2-2 Figure 6.2 Figure 11.5-1 ligure 6.3 Figure 3.73-54 Figure 6.4 (Sheet 1) Figure 9.5-38 Figure 6.4 (Sheet 2) Figure 9.5-39 Figure 6.4 (Sheet 3) Figure 9.5-40 Figure 6.4 (Sheet 4) Figure 9.5-41 I 4 p.m. i W) ) i REVISION 3 ! x MAY 21,1982 i $ . . _ . . . _ m . . ~ , . . , _ . _ _ . . ~ _ . . .

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 !                                                 PREFACE The objective of the Comanche Peak Steam Electric Station (CPSES)

Energency Preparedness Program illustrated by the Emergency Plan is to protect the health and safety of the general public, persons i temporarily visiting or assigned to the station, and station employees in the event of an emergency at the Station. To meet this objective, this Plan creates a high order of preparedness and ensures an orderly and tinely decision-making process in times of stress. Emphasis is placed on maintaining energency preparedness through training,

,              exercises, and drills.      It further assures the availability of equipnent, supplies, and essential services. This Plan also provides for the coordination of onsite and offsite emergency response efforts.

Specific details for the executioa of the Energency Plan are incorporated into implementing procedures, referred to as Emergency Plan Procedures. While this docuuent outlines the overall aspects of t- emergency planning, the Emergency Plan Procedures contain specific i individual responsibilities and detailed instructions for accouplishing specific tasks. A list of the Emergency Plan Procedures l is contained in Section 15.0, Appendix K. The Emergency Plan provides the direction and coordination of the Energency Organization. Energency Plan Procedures are used to detail the various job functions in suppc et of the Emergency Plan and to assure a smooth transition from a cornal node to an emergency mode. . 1 The assignment of key personnel and alternates to the job functions is discussed in this Energency Plan. Additional assistance is provided ] 4 to the onsite group by offsite company personnel, local, sente, and federal agencies, and contract personnel as required. } The normal organization of station personnel is discussed in Section j 1.0 of this Plan, describing and assigning the bumediate onsite ] positions of responsibility, and noting the authority and i responsibility for declaring an energency. Upon the declaration of an h Emergency Action Level, the individuals in the normal operating j organization assume responsibilities in the Emergency Organization. j Selected criteria are established to promptly determine the Energency 1 Action Level. The Energency Action Levels for CPSES are Notification ] of Unusual Event, Alert, Site Area Energency, and General Emergency. l , The degree of involvement of onsite, local, state, and federal 1 L L 4 1 j - k) j-e ] $ REVISION 3 3 MAY 21, 1982 H e v.= =:==: - - - -- - -+ - m - --- ,-~n nm

t r () CPSES/EP personnel is dependent upon the declared Energency Action Level. At j the least severe end of the emergency spectrum, Notification of Unusual Event, the situation may have no potential for escalation to a more severe emergency condition and there may be no effect on the Station operating status. The response to this situation should involve only onsite personnel and would not necessitate the mobilization of the offsite Energency Organization. If the energency falls in a classification such that offsite consequences may require

protective action, then local, state, federal agencies,-and additional I company personnel would be involved as described in this Plan to

! assist in the nitigation of the emergency. Activation of the Offsite l Emergency Organization will be initiated in the event of an Alert i condition or higher. This plan does not address itself to operation of the station i equipment as this is adequately covered in operating, abnormal operating, and emergency operating procedures. This Plan and its implementing procedures are designed so that they do not interfere with the objectives of the Security Plan. The CPSES Energency Plan is designed to conplement Appendix 7 to Annex L of the Texas Emergency Managenent Plan and to interface with the Hood and Somervell County Emergency Operations Plans. The Conanche Peak Steam Electric Station Energency Plan is designed to provide guidance when confronting an emergency. The Emergency Flan Procedures provide guidance and specific information to ensure the purpose of the Energency Plan is achieved. The Energency Plan reflects nanagenent's recognition of a need to cope with a broad i spectrum of potential consequences and prescribes the actions necessary for onsite personnel to activate support groups and establish connunications in a timely manner to protect the public and this station. i i 2 k / p l REVISION 3 MAY 21, 1982

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i 1.0 ORGANIZATION The Comanche Peak Steam Electric Station Organization is structured to form either the normal operating organization or the CPSES Emergency Organiza tion. In support of this organization there are offsite emergency groups formed by the Texas Utilities Corporate structure, and the local, state and federal governments. The functional interfaces among these organizations are illustrated in Figure 1.1. The responsibilities of each agency and key individuals are delineated , below. j 1.1 NORMAL OPERATING ORGANIZATION _ __ _ __ l The CPSES staff organization is shown in Figure 1.2. The Manager, Plant j Operations is in charge of CPSES and is responsible for its operation. j In his absence, one of the following persons will assume the i responsibility for the operation of the Station. ? Operations Superintendent i j Engineering Superintendent l Maintenance Superintendent } Administrative Superintendent ! During backshift and weekend periods when the above personnel are not onsite, the Shift Supervisor is responsible for all activities at CPSES. Figure 1.3 illustrates the TUGCo Nuclear Organization which provides j support and training to the CPSES staff organization. l 1.2 CPSES EMERGENCY ORGANIZATION i j In the event of an emergency situation, the Shif t Supervisor is the ! individual responsible for initiating the CPSES Emergency Plan in i accordance with procedures and as he deems appropriate. He shall i' endeavor to maintain the Station in a safe condition, take action to protect the health and safety of the public and the Station personnel, and call for assistance as needed or as required by the Plan. At the onset of an emergency situation, the Shift Supervisor, who is onsite 24 i hours per day, is designated the Emergency Coordinator and serves in [ this capacity until re,lieved by the Manager, Plant Operations or a ! designated alternate. Station personnel who are members of the f Emergency Organization are notified as specified in the Emergency Plan l Procedure EPP-203 " Emergency Notification and Communications" and L 1-1

s E s REVISION 3

MAY 21,1982 e

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I l l l l CPSES/EP G EPP-204 " Emergency Facility Activation". These procedures provide the notification instructions and emergency facility staffing requirements pursuant to the declared Emergency Action Level. An up-to-date call list is maintained in the Control Room, Technical Support Center (TSC), Emergency Operations Facility (EOF), and the Central Alarm Station (CAS). Other call lists used to notify offsite officials and request offsite assistance are maintained in EPP-203

                   " Emergency Notification and Communications". The CPSES Emergency Organization, shown ,in Figure 1.4, illustrates the overall organizational structure. Table 1.2 lists the emergency functions and illustrates a graded emergency organization response for each Emergency Action Level.           The emergency facilities are described in Section 6.0.

i 1.2.1 CPSES EMERGENCY ORGANIZATION - RESPONSIBILITIES AND AUTHORITIES 1.2.1.1 Emergency Coordinator The Emergency Coordinator has the responsibility and authority for continued evaluation, coordination and control of all onsite activities related to an emergency until the recovery organization is formed. The responsibilities assigned to the Emergency Coordinator are:

a. Assess the plant status and determine the required Emergency Action Level.

b. Notify the NRC, DPS in Waco, and any other emergency l organizations as appropriate.

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c. Activate and direct the CPSES Emergency Organization.

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d. Establish and maintain communications with the offsite emergency operations centers. Also provide utility contact for those
Federal, State, and Local authorities who will be at the EOF.: e. Ensure that the CPSES Emergency Organization is fully and correctly staffed.

i i f. Evaluate the offsite radiological conditions in order to , recommend evacua. tion or other protective actions to the offsite j authorities. i l 1-2 () REVISION 3 MAY 21,1982

l l CPSES/EP (~)

g. Promptly notify the State and/or local officials of the projected dose to the population-at-risk based on the Emergency Action Level.

h. Personnel accountability with the assistance of Security and each department supervisor or senior individual.

1. Designate personnel within the organization to maintain logbooks of significant events, actions and data.

j. Authorize all re-entries into evacuated onsite areas.

k. Concurs with all public information and/or news media releases made from CPSES.

1. Supports and assists efforts by Federal, State and local personnel both at the EOF and at the various other emergency operations centers.

m. Coordinates all offsite CPSES emergency response activities with those activities conducted onsite.

n. If the EOF is activated, he directs those activities conducted from the EOF.

The Emergency Coordinator shall not delegate his decision making authority for notifying or making recommendations to the offsite authorities concerning evacuation or other protective actions, or for re-entering evacuated onsite areas. The line of succession for the Emergency Coordinator when the Manager, Plant Operations is unavailable is as follows: Engineering Superintendent Maintenance Superintendent Operations Superintendent t Operations Engineer Shift Supervisor, on duty 1-3 m

f REVISION 3 j MAY 21, 1982 __ _ _ _ _ _ ~ -

CPSES/EP For each Emergency Action Level (EAL), an individual is assigned the position of Emergency Coordinator (E.C.). The initial E.C. is the Shift Supervisor, regardless of the EAL. When the emergency escalates, the other emergency facilities are activated accordingly and the duties and responsibilities of the E.C. are transferred to the facility manager as soon as practical. The transfer is consummated by an exhange of information between the emergent E.C. and the current E.C. concerning current reactor status and mitigating actions taken or in process. The Emergency Coordinator shall retain these responsibilities until the Recover Organization is functional and a similar exchange occurs between the E.C. and the Recovery Manager. 1.2.1.2 Canmunications Coordinator Emergency Communications consists of telecommunications to and from onsite and offsite response organizations that are pertinent to the mitigation of the emergency. These communicatons shall be logged for 3 the purposes of collecting and preserving historical information. A description of the communications system is in Section 4 " Emergency Communications" . An individual in each CPSES emergency response facility, designated as a communicator by that facility manager shall handle emergency communications. The responsibilities of the communicators *as specified in EPP-203 " Notification and Communications" include: coordinating onsite communications, maintaining communications with the principle offsite response organizations, logging communications, seeking additional assistance and equipment through the Emergency Coordinator and assisting the facility manager as necessary. This procedure also provides support organization call lists, emergency message formats for use by the communicators and explanations on the operation of the equipment. Control room personnel make the initial contact with the offsite response organizations as prescribed by the notification procedure and as instructed by the Emergency Coordinator. Upon activation of the TSC and EOF, the primary ' ommunications c responsib;11ty shall transfer to these facilities with the EOF ultimately becoming the conmunications center. To facilitate communications, the communicator in the EOF shall be the Communications Coordinator. Communicators in the other facilities shall continue as instructed by the facility manager. Functions of the EOF Communications Coordinator include: 1-4 h REVISION 3 MAY 21,1982 _.m m, ,

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a. Coordinating and directing the activities of those communicators

() stationed at the EOF.

b. Ensuring that communications procedures are properly implemented and that records of incoming and outgoing messages are maintained by CPSES emergency response personnel.

c. Ensuring that communications within the CPSES Emergency Response Organization and wf th the Federal, State, and local emergency response organizations are maintained.

d. Initiating requests for any assistance required for the repair and maintenance of communications equipment through the Logistical Support Coordinator.

e. Initiating requests for additional communications equipment required through the Logistical Support Coordinator.

f. Providing general support to the Emergency Coordinator as required.

1.2.1.3 Public Information Coordinator The Public Information Coordinator is responsible for and has the authority to coordinat.e information releases made to the news media. The Public Information Coordinator may also handle rumors. He reports to the EOF during a Site Area or General Emergency. The official company spokesman at CPSES shall be the Manager, Nuclear Operations or his designated alternate. Procedure EPP-212 " Release of Emecgency Related Information to the Public", provides instructions to the Public Information Coordinator concerning the notification of the news media, arranging press releases and coordinating the information to be released with corporate, Federal, State and local public information personnel. The Public Information Coordinator assists the Emergency Coordinator in the following items:

a. Activates the Media Center.

b. Formulates all TUCCo news releases concerning the emergency condition, insuring that they are up-to-date and technically accurate; and assists the CPSES spokesperson in their presentation.

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c. Coordinates news releases and rumor control activities with county and state public information personnel.

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d. Coordinates with the Emergency Coordinator to obtain approval for i all news releases.

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 ,                    e. Arranges and coordinates any press conferences conducted at the Media Center.

f. Acts as a liaison between CPSES and Corporate public information personnel.

1.2.1.4 Security Supervisor The Security Supervisor is responsible for and has the authority to

 ;                    coordinate the following security activities:

I

a. Security of the entire plant site.

b. The movement and badging of all personnel entering the site to i provide support.

c. Ensure that all non-essential site personnel are evacuated and that unauthorized personnel cannot enter the site.

1

d. Assist with the implementation of any security requirements j imposed upon offsite support required by the plant (e.g. medical j or fire). ,

'I l e. Coordinate the assembly and accountability of personnel at the designated plant assembly point.

f. Initiate personnel accountability procedures and maintains

.; accountability records during the emergency.

g. Coordinate search and rescue efforts with the Operational Support Center (OSC) Supervisor.

Security personnel are responsible for maintaining station security, for controlling site and vital area access and for maintaining personnel accountability information. Selected security personnel are members of the station fire fighting team. 'l I 1-6 I b t REVISION 3 MAY 21,1982 l 4

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CPSES/EP j The Security Supervisor or his designated alternate may contact the j local or state law enforcement agencies as necessary. A Security j i Coordinator is the primary alternate to the Security Supervisor. Their emergency duty station is the EOF during a Site Area or General i1 Eme rgency. i 1.2.1.5 Logistics Support Coordinator I The Administrative Superintendent is responsible for and has the j authority to inplement the following functions: I

a. Coordinates, directs and responds to requests for administrative and logistical assistance from the CPSES Response Organization.

] b. Coordinates recall and deployment of administrative support personnel as needed to respond to the emergency. 4

!                            c. Ensures that the general needs of emergency response personnel are j                                   met (e.g. , commanications and equipment repair, food, sleeping facilities, office supplies, etc.).
,                            d. Ensures the timely completion of all offsite logistical assistance provided in support of emergency response and recovery efforts.
;                            e. Supervises and coordinates the retrieval of drawings and documents t                                   for the CPSES Emergency Organization.

I f. Ensures that onsite records management support and recordkeeping efforts are being carried out. ..l

g. Arranges transportation and temporary housing for support personnel as needed.

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!                            h. Aids emergency communications personnel in obtaining additional l'                                  communications equipment as needed.

Administrative personnel shall be available to temporarily relieve members of the CPSES Emergency Organization. Also, they shall be available as necessary to operate communications and office equipment. Administrative personnel are individuals from the accounting and warehouse groups and from the secretarial pool. l 1-7 l I

i REVISION 3 MAY 21, 1982 i

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_ _ - ... _ - - - - - . m > z =.u ;w 1a v CPSES/EP The alternate for the Administrative Superintendent is the Administrative Supervisor. The Logistical Support Coordinator reports to the EOF during a Site Area or General Energency. 1.2.1.6 Radiation Protection Coordinator The Radiation Protection Coordinator has the responsibility 4.nd the authority to exercise the following functions:

a. Provide environmental, radiological, and health physics support to the emergency response effort.

b. Coordinate the TUGCo onsite and offsite radiological monitoring e f forts.

c. Ensure that emergency sampling, radiological monitoring, radiological safety, bioassay, access control, and decontamination procedures are properly implemented.

d. Ensure that personnel radiation exposures are maintained in accordance with plant administrative limits and 10 CFR, Part 20 limits, except when authorized by the Emergency Coordinator for

                     . life saving or an urgent plant emergency situation.

e. Assist in plannirg personnel rescue operations, if necessary.

f. Assist in the transfer of injured and non-essential personnel if radiation or contamination hazards are involved.

g. Reque st, through the Engineering Team Coordinator, any engineering evaluations of temporary shielding on special tools and equipment.

h. Request, through the Logistical Support Coordinator, the following as necessary:

1. Additional r adiation monitoring equipment.

2. Additional health physics support personnel.

3. Additional instrumentation and equipment as required.

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1. Advise the Emergency Coordinator on matters involving radiological sa fe ty.

J. Review and evaluates all radiological data, including appropriate chemical and radiochemical results.

k. Maintain appropriate records of radiological monitoring and dose assessment activities.

1. Coordinate the TUGCo offsite radiological assessment activities with those of the counties and State.

m. Correlate, assesses and predicts current and anticipated release rates and radiation levels.

n. Assist the Emergency Coordinator in the formulation of

recommendations to be submitted to the counties and State regarding the protective action measures to be implemented.

o. Obtain current meterological data and determines its effects upon the radiological release and dose projections.

p. Provide the Public Information Coordinator with an accurate assessment of the radiological situation which is suitable for release to the public.

The Chemistry and Environmental Engineer alternates with the Radiation Protection Engineer in the EOF during a Site Area or General Emergency. The Radiation Protection Section is responsible for all aspects of radiation protection. Designated individuals within the section shall provide an interface between the Radiation Protection Engineer and the Emergency Radiological Teams. A Radiation Protection Technician on shif t shall be qualified to bnplement radiation protection and chemistry sampling procedures and to perform the necessary radiological surveys until additional Radiation Protection or Chemistry personnel arrive on site. Radiation Protection personnel shall also be qualified in the methods of decontaminating personnel, equipment and areas. The decontamination effort may also involve personnel from the Operations and the Maintenance Departments. The on-shift Radiation

Protection personnel shall respond promptly to 1-9

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l the Emergency Coordinator's requests during emergency situations. I 1.2.1.7 Onsite Radiological Coordinator The Onsite Radiological Coordinator is a technician from the Radiation Protection staff who reports to the Radiation Protection Coordinator. His duty station is the EOF during a Site Area or General Emergency and he is responsible for the following:

a. Ensures that emergency sampling and radiological survey procedures are being implemented, and that the resultant information is available to the Emergency Operations Facility, Technical Support 6

Center, and Control Room. i

 !                  b.             Accumulates, tabulates, and evalutes data on plant conditions, I

such as meteorological and area radiation monitoring readings, and f radiation survey results. I

c. Ensures that the use of protective clothing, respiratory protection and access control within the plant is implemented as deemed necessary.

d. Ensures that appropriate bioassay procedures have been haplemented for onsite personnel when a radiological incident has occurred.

e. Ensures that personnel radiation exposures are maintained in accordance with plant administrative limits and 10 CFR, Part 20.

f. Ensures that personnel are properly decontaminated, if necessary.

g. Assists in planning personnel rescue operations, if necessary.

h. Assists in the transfer of injured and non-essential personnel if radiation or contamination hazards are involved.

1. Requests through the Radiation Protection Coordinator the following as necessary:

J 1. additional radiation monitoring equipment. 3

2. engineering evaluations of temporary shielding on special

,                                      tools and equipment.
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CPSES/EP 8 I. 9 3. additional health physics support personnel. l ( 4. additional instrumentation and equipment as required. 5 { j. Advises the Radiation Protection Coordinator on matters involving j radiological safety. I" k. Reviews and evaluates all onsite radiological data, including appropriate chemical and radiochemical results.

1. Maintains appropriate records of onsite emergency response activities.

} f 1.2.1.8 Offsite Radiological Coordinator - The Offsite Radiological Coordinator is a technician from the Radiation Protection staff who reports to the Radiation Protection Coordinator during a Site Area or General Emergency. His duty station is the EOF and his principal functions are: a. Coordinates and directs the activities of the TUGCo offsite radiological monitoring teams.

b. Receives radiological survey data obtained by the radiological monitoring teams.

c. Coordinates with TUCCo offsite radiological assessment activities with those of the counties and State.

) d. Correlates, assesses and predicts current and anticipated release rates and radiation levels. e. i Assists the Radiation Protection Coordinator and Emergency

;                      Coordinator in the formulation of recommendations to be submitted I

to the counties and State regarding protective action measures to be implemented. 3 j f. Obtains current meteorological data and determines its effects j upon the radiological release and dose projections. j j

g. Provides input and advice to county and State radiological monitoring teams xegarding ingestion pathway monitoring (e.g. ,

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CPSES/EP q}} vegetation, water and milk supplies).

h. Maintains appropriate records of radiological monitoring and dose assessment activities.

1.2.1.9 Technical Support Center Manager A The Technical Support Center (TSC) Manager has the responsibility and authority to manage the onsite emergency activities required to bring the plant to a safe shutdown condition. Specific responsibilities of the TSC Manager are: l

a. Directs the operation of the Technical Support Center.

b. Relieves the Control Room personnel of the administrative functions and decisions.

i c. Assumes control of coordination and direction of all onsite activities conducted from the TSC including:

1. establishment of proper communications with the Control Room, Operational Support Center, Emergency Operations Facility, and other emergency response facilities as appropriate.

2. determination of the extent of the emergency and the current status of the emergency response actions.

3. coordination and direction of all emergency response operations performed by TUGCo personnel within the protected area of the site.

d. Receives and distributes plant status and technical information received in the Technical Support Center.

e. Maintains communications with the Emergency Coordinator in order l

I to provide plant condition information, to review any plant manipulations that might affect offsite consequences and to recommend offsite protective actions. i f. Coordinates Engineering and Maintenance support of emergency I response activitie's.

i 1-12 O

l REVISION 3 ' MAY 21,1982 1

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CPSES/EP (h g. Initiates rescue or repair / damage control operations as appropriate.

h. Provides input to NRC representatives in the TSC regarding plant operating license requirements.
The TSC Manager is the Operations Superintendent. His alternate is the Operations Engineer.

1.2.1.10 Technical Support Center Advisor - The Technical Support Center Advisor is responsible for the following functions:

a. Coordinates the emergency repair and damage control effort with the Operational Support Center (OSC) Supervisor.

b. Maintains an up-to-date knowledge of plant status and communicates this information to the TSC Manager, Engineering Team Coordinator,

 !                   and all other concerned parties.

c. Coordinates the resesrch and information gathering effort of any required technical data which may be provided by industry and other country-wide sources. i

d. Verifies technical accuracy and adequacy of all public information releases prior to their dissemination to the media.

e. Assists the Engineering Team Coordinator in the technical assessment of plant status and emergncy conditions.

l i This position shall be filled by the Maintenance Superintendent, the Maintenance Engineer or the Reactor Engineer. 1.2.1.11 Engineering Team Coordinator i An Engineering Team is managed by the Engineering Team Coordinator } whose primary function is to interface between the engineering team and the TSC Manager. He is also responsible for the following:

a. Verifies that emergency response engineering support personnel with TSC assignments are in position, or have been notified and are proceeding to the TSC.

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b. Assumes the detailed direction and coordination of the Engineering Team.

c. Coordinates and directs efforts to technically assess plant status and emergency conditions.

d. Advises the Emergency Coordinator and TSC Manager on technical matters relating to the NSSS, fuel integrity, plant systems and equipment, and electrical systems and instrumentation.

Personnel such as the Results Engineer, the I&C Engineer or the Engineering Superintendent shall perform these functions. 1.2.1.12 Engineering Team The Engineering Team assenbles in the Technical Support Center and is composed of engineers of various disciplines and specialists from different departments. As a minimum, the team shall consists of four members with backgrounds in nuclear, mechanical and electrical engineering, and operations. The primary function of this team is to evaluate plant parameters and radiological conditions, both historical and current, and recommend corrective or preventative actions to the Engineering Team Coordinator. 1.2.1.13 Technical Support Center Health Physicist The Technical Support Center Health Physicist is a Health Physicist from the Radiation Protection section. In addition to performing the functions of the Onsite Radiological Coordinator in the TSC, he also coordinates initial onsite radiological monitoring efforts until the activities can be reassigned by the Radiation Protection Coordinator and provides Radiation Protection expertise to the Engineering Team and the Technical Support Center Manager. 1.2.1.14 Operations Support Center Supervisor The Operations Support Center (OSC) Supervisor is responsible for the following:

a. Activates and establishes communications at the Operations Support Center.

1-14 b REVISION 3 MAY 21,1982 j _., _ .,.m -.---r,.-.,..

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b. Supervises those per:onnel assigned to the OSC and maintains a reserve operating staff.

c. As instructed by the TSC Manager, dispatches personnel to assist in repair / damage control activities, radiation surveys, rescue operations, establishing control areas, and initiating recovery actions.

d. Coordinates the emergency repair and damage control effort with the TSC advisor.

] The OSC Supervisor shall be the Mechanical Maintenance Supervisor. The Electrical Maintenance Supervisor is his alternate. j 1.2.1.15 Operations Support Center Personnel Operations Support Center Personnel, provided by the Mechanical, the i Electrical and the Instrument and Control sections, supplemented by Radiation Protection and Operations personnel, are assigned the ] responsibilities of emergency repair, damage control, first aid, rescue and operations support. The Emergency Repair and Damage Control Group 4 (ERDC), under the direction of the OSC Supervisor, shall effect any repairs or modifications necessary to mitigate the emergency condition,

.                      to minimize the damage and to initiate recovery actions. The ERDC I                     Group is also capable of performing rescue operations and providing first aid treatment.

When the ERDC Group is unavaileLie, Operations personnel may initiate 1 temporary damage control mes:,ures, perform rescue operations and 1

,                      perform initial first aid treatment.

1 i 1.2.1.16 Station Operations and Fire Fighting j j The Operations Department is responsible for all Station Operations. j The normal operating crew (see Appendix A) is able to handle emergency

operations and is capable of aiding in other area of emergency response. Off duty operations personnal shall be called upon as necessary to augment the on-shif t operation crew. At all times, the

 ,                     Shift Supervisor or his designated alternate, is in charge of the

[ control room unless he is properly relieved by a qualified company ] individual. . I 1 . 4 {, 1-15 . b 1 REVISION 3 MAY 21,1982 s

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,y mw.im.um . u m e. m m e a o -w -. --um . murumm h ! i I 1 U '. CPSES/EP h () !! The Operations Department and Security personnel and augmented, if required, by the local volunteer fire departments, shall provide a five man fire team on each shift in accordance with the CPSES Fire i j: Protection Program. Operations personnel are also available to assist j

'!                           the ERDC teams as necessary.                                                                l Q                         .

L; A record of all significant Operations events shall be recorded by the h operating crew in a Control Room log book. i. 1.2.1.17 Shift Technical Advisor l

i

.I A Shif t Technical Advisor (STA) shall be assigned to each operating i Il shift and be capable of ' reporting to the control room within minutes. ; F The STA's functions include evaluating plant conditions and providing ' advice to the Shift Supervisor during plant transients, accidents, and q on matters related to Operational Safety. lt ,t During energency situations, after the TSC is functional (refer co 'l Section 6), the primary responsibility of the STA is to advise the Shift Supervisor shall be transferred to the TSC-Manager. The STA l' shall resain in the control room and shall continue in a supplemental advisory and technical support role to the Shift Supervisor. The STA is also available to confer directly with the Emergency Engineering Team and to be a liaison between the TSC and the Shift Supervisor. 4 1.2.2 MANPOWER AVAILABLE FOR EACH EMERGENCY ACTION LEVEL The minimum staffing requirements for an emergency are shown in Table l, 1.1. Table. l.2 illustrates the emergency organization response for j '; each Emergency Action Level to ensure that the all emergency functions j, are satisfied. l,

< 1.2.3 i!

CORPORATE SUPPORT (( In addition to the Comanche Peak Steam Electric Station staff, the j Texas Utilities Company System has numerous resources which are i available to support CPSES during an emergency or during the recovery phase of operations following an emergency. The Emergency Coordinator j is the individual onsite who will request Corporate support services as required by the emergency condition. This request will be made to the

 }                        Vice-President Nuclear,. the Recovery Manager or their designees. The d                          required resources shall be made available by TUGCO-Nuclear Operations, i,

t 1-16 ? [ o, Cl) I REVISION 3 l MAY 21,1982 1 1 e l

_ _ _ . - . . _ . _ _ _ _ . _ _ . ~ . . . . . _ . , _ . . _ _ _ _ . _ _ _ . . _ _ _ _ _ _ __ . - - . _ . - l CPSES/EP (3) w TUGCO-Lignite Operations, or other Texas Utilities Company departments, ! when requested by the TUGC0 Vice-President, N iclear, the Recovery l Manager or their designated alternate. The a ce-President, Nuclear, in addition to the above activities, also supports the CPSES Emergency Organization in the following: j a. Interfaces with TUGCo Corporate management to obsain policy decisions in a timely manner and to ensure that all TUGCo resources are available to support the emergency response and recover efforts.

b. Maintains close contact with personnel located in the corporate offices to keep them informed of the progress of the emergency response and recovery efforts.

c. Responds to requests from the Emergency Coordinator.

I d. Acts as a liaison between TUGCo and those governmental officials not directly involved in the emergency response or recovery

e f forts.

I The following is representative of the support available from the above resources: ! 1.2.3.1 TUGC0 Nuclear

a. Engineering and Administrative Services: approximately 5 mechanical, nuclear and electrical engineers.

b. Nuclear Operations staff: An Independent Safety Analysis Group, approximately 12 engineers - nuclear, mechanical, electrical, j civil and architectural engineers with experience in Plant Operations, Fire Protection, Chemistry and Radiochemistry, Shielding Design, Instrumentation and Controls, Transient Analysis and System Interaction, Structural Design, Thermal Hydraulics, and Mechanical and Electrical Systens.

c. Health Physics: approximately 4 Health Physicists to assist the plant Radiation Protection staff and perform independent analyses.

d. Quality Assurance: The TUGC0 Quality Assurance Department shall provide personnel to assist recovery operations.

i. i 1-17 i (* , f ' '~ i r REVISION 3 j MAY 21,1982 4 y r . .,, m wg., - ..y ,.y- m . m ,y y -.<v n p --r y mr. m mmggg_.3 - .~ _

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} CPSES/EP l 1.2.3.2 TUCCO-Lignite Operations O' t l l TUCCO currently operates 8 lignite fueled units at three locations each ! j of which has associated mining operations. This group is capable of , l furnishing personnel, equipment and supplies when required. Equipment i } available includes: bulldozers, scrapers, front-end loaders, dump

trrcks, fork lifts, mobile lifting equipment, pumps and air j compressors.

{ ! Electricians, mechanics, instrument and control technicians, and ! chemistry technicians are available for assistance to CPSES if requested. t , i j 1.2.3.3 Other Texas Utilities Support Organization ! a. Texas Utilities Services, Inc. - TUSI Engineering and l Construction shall provide technical and analytical support i required by the plant staff, including design modifications of i systems and structures, to ensure the plant can be maintained in a safe condition. . TUSI Engineering and construction will furnish l manpower, tools, equipment, and materials for engineering and j construction services to provide temporary facilities, power, and i e communication services as required. ! TUSI Engineering and Construction maintains an on-site staff of i approximately 50 experienced engineers in the following i disciplines: nuclear, mechanical, electrical, instrumentation i and control, and civil.

b. Legal - The law firm of Worsham, Forsythe and Samples has been i

retained by Texas Utilities to provide legal assistance and support regarding CPSES. If needed, in the event of an emergency condition at CPSES, Worsham, Forsythe and Samples shall provide j legal ~ assistance for the handling of claims and litigation, and i in providing legal counsel for other Company actions regarding 1 the emergency. I c. Insurance - The TUSI Risk Management and Insurance Department shall advise other groups and departments of those activities involving TUCCO's nuclear property insurance, property loss control, and damage cost accumulation, and coordinate activities involving TUCCO's liability insurance carrier. They shall a investigate all injuries to Company personnel and the public, and ) major incidences of property damage to establish cause. 1-18 ! REVISION 3 ( MAY 21,1982 1 I t-.,._~.

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d. Purchasing - The TUSI Purchasing Group shall provide materials, contract services, and transportation support functions. They shall contact the appropriate State and county agencies to determine travel conditions for transportation of personnel and j equipment to the site.

e. Sccurity - The Director, Corporate Security, shall have the y responsibility for providing security for news conferences in

] Corporate office facilities, augmenting the site security j) supervisory staf f, and assisting the site Security Supervisor in ! obtaining additional contract security personnel. N f. Human Resources - The TUSI Human Resources Group shall provide i! and coordinate additional manpower in support of an emergency i response effort.

h j g. Environmental Group - The TUSI Environmental Group shall provide h support in environmental monitoring. This support may be in the j form of additional personnel to take vegetation and ground gi samples for radiological analysis during the post-accident sampling of the ingestion exposure pathway, providing technical [gf expertise for enviromental analysis, or providing contact with I additional testing laboratories.

h. Public Information - The Texas Utilities Information Services g Group shall coordinate information and news releases to the news media with local, State and Federal officials and agencies. A

 .c cooperative effort between the Director of Information Services and the Public Information Coordinator at the site EOF shall ensure a timely coordination of this task.

4 1 1.3 EMERGENCY RESPONSE SUPPORT ORGANIZATIONS l The following private, local, State and Federal agencies provide j personnel to support or augment the CPSES Emergency Organization. When personnel from these agencies are on the Station property, they are subject to the authority of the Emergency Coordinator. This means that I for reasons of safety and security, they shall commence or cease their

actions when so directed by the Emergency Coordinator.

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l 1 i CPSES/EP h 1.3.1 LOCAL AGENCIES 1 The key emergency planning organizations involved at the local level with emergencies at CPSES are the Hood and Somervell County Emergency Organizations. These organizations are responsible for protective measures for citizens in their respective counties. Each organization consists of numerous agencies which perform various duties during an j accident. The County Judge is in charge of the emergency organization and directs the operations of the agencies described below. Letters of agreement with individual agencies delineate their support and are included in Section 15.0, Appendix H. Each county has an " Emergency Operations Plan" and " Manual of Emergency Procedures" which are - predicated on the county's ability to respond and which prescribe a response based on the declared emergency action level. i 1.3.1.1 Sheriff's Department Agreements have been reached with the Somervell County and Hood County Sherif f's departments to support the CPSES emergency response with a commitment of officers and vehicles to assist in evacuation efforts, traffic control, and security. The $heriff's departments are also responsible for county communi-2 cations during an accident including notification of the county 1 officials needed for the emergency organization. The Sheriff's office will be used as the primary County Emergency Operations Center (EOC) in their respective counties. 1.3.1.2 Fire Department i Local fire fighting support is provided to CPSES through written agreements with the Somervell County Fire Department in Glen Rose and

the Granbury Fire Departsent. The two organizations consist of a total force of approximately fifty volunteers. Each can respond to the site in approximately thirty (30) minutes with at least one truck. The Somervell County Fire Department is located eight road miles from CPSES 1 and is the primary contact if offsite support is required. The Granbury G Fire Department is located sixteen road miles from CPSES and provides F additional support as required.

j 1.3.1.3 Ambulance Service Written agreements with the Glen Rose /Somervell County Volunteer Fire Department Ambulance Service and the Hood General Hospital Ambulance n REVISION 3 1-20 ) i MAY 21, 1982 i 4 6,_,. _ . _ _ . -- . - r -s - - -

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)                 Service describe their support in providing back-up assistance .to the i

i CPSES emergency vehicle to transport victims for medical assistance. Hood General Hospital Ambulance Service can provide one (1) ambulance 1 with an EMT and paramedic in 30 minutes. Somervell County can provide i one (1) ambulance in 30 minutes.

1.3.1.4 Medical Support Hood General Hospital in Granbury, Texas, is located approximately sixteen road miles from CPSES. A letter of agreement has been obtained from Hood General to receive and treat injured personnel from CPSES who are contaminated with radioactive material or who have an overexposure

' requiring medical evaluation. The Hood General Hospital facilities can handle at least five injured persons simultaneously. Backup medical services, support and definitive care are provided through a contract l and a letter of agreement with Radiation Management Corporation and their affiliated hospital at the University of Pennsylvania. { Injured personnel whose medical treatment is not complicated by radiological considerations may be sent to either Hood General Hospital i or Marks English Hospital, which is approximately eight road miles } distant, in Glen Rose, Texas. Medical support for CPSES is discussed in greater detail in Section 10.0. 1.3.2 STATE AGENCIES 1.3.2.1 Texas Department of Health The Bureau of Radiation Control of the Texas Deparunent of Health (TDR) is the responsible agency in the State of Texas for radiological ene rgencies. Radiological emergency planning is contained in Appendix 7 to Annex L of the Texas Emergency Management Plan. In the event of an emergency condition at CPSES, the TDH is notified by the DPS office in Waco. l l Direction and control for overall State agency activities is the l responsibility of the Director, Division of Emergency Management. l Emergency Radiological response is the responsibility of the Chief, Bureau of Radiation Control. I l l l l l 1-21 REVISION 3 MAY 21,1982

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t CPSES/EP l Upon notification of a General Emergency at CPSES, the TDH shall send a O l Response Team to the 10-mile EPZ under the direction of the Chief of Field Operations. This Response Team is capable of supporting the emergency organization in the following areas: 3

a. Environmental and radiological monitoring, including bringing a mobile radiological laboratory to the site. (It is expected that l this mobile laboratory can be onsite in approximately four (4) hours.)

b. Assessment of of fsite hazards and protective actions.

1.3.2.2 Texas Department of Public Safety l A written agreement uith the Texas Department of Public Safety (DPS) confirms their support for the CPSES Emergency Plan. The District Commander of the DPS will provide support to local law enforcement agencies for the evacuation of the public from the EPZ. The commucications network of the DPS is essential in coordinating with local agencies such as sheriff and fire departments within the 50 mile EPZ. The area around CPSES is under the jurisdiction of the Region 6A Headquarters in Waco. . 1.3.3 FEDERAL AGENCIES The Nuclear Regulatory Commission (NRC), Federal Emergency Management Agency (FEMA) and Department of Energy (DOE) are the primary Federal I response organizations in the event of an emergency at CPSES. f Additional Federal agencies, such as the Environmental Protection Agency, Federal Aviation Administration, Department of Commerce, ( National Weather Service, et al, may provide ancillary services and support to the primary agencies. Management of the Federal response, which is divided into technical or radiologic.tl aspects and non-technial aspects, requires the coordination of the three primary agencies with each other, with Texas Utilities officials and with State and local authorities. NRC and DOE are responsible for the technical h response and FEMA for the non-tec* nical response; the overall responsibility is shared by the three primary agencies. i f t REVISION 3 1-22 MAY 21,1982 i . i M M9ev rw e=w h ***W.= e cay 4 9 _ ** " ~ _ _ *4**--v*='* ** - * + + ' * > - Ng vw - MW

, m . m.. _ . - - -_ _ s 1 6 - CPSES/EP ' v'N 1 Q) To support Federal response efforts, the following facilities are l available within sixty (60) miles of CPSES.

Airports: Granbury, Cleburne, Stephenville, Meacham in Fr.

Worth, Love in Dallas and Dallas-Ft. Worth Regional 1 { Motels: Glen Rose, Granbury, Cleburne, Stephenville, Fort i Wbrth and Dallas I CPSES: Space available in and near the EOF, telephone lines and electrical service connections for equipment brought to the site to be used by the Federal . agencies. I l 1.3.3.1 Nuclear Regulatory Commission The Nuclear Regulatory Commission (NRC) reviews and approves the CPSES radiological emergency response plan and program and evalutes the compatability of the CPSES plan with the State and the local emergency plans. The NRC, because of its familiarity with CPSES operations and reactor specific terminology, is responsible for coordinating the overall technical aspects of the Federal response. Primarily, NRC activities are focused on the activities occurring onsite and the mitigation of the emergency. Upon receiving notification of an emergency, the NRC will respond pursuant to the emergency classification. If a Site Area Emergency or General Emergency has been declared, the NRC dispatches emergency response personnel to the site. l 1.3.3.2 Federal Emergency Management Agency The Federal Emergency Managem at Agency (FEMA) provides assistance to > the state and local governments in the preparation, review and testing of radiological emergency response plans. FEMA is also the normal l interface between other Federal agencies and the local governments. I ! FEMA coordinates the non-technical aspects of the Federal response. l This includes assistance to Federal, State, and local organizations in j matters such as transportation, communications and housing, implementing offsite protective action measures and other matters not f i i 1-23 REVISION 3 MAY 21,1982 l r , -s. l l > ~ n -r-_~~m m_t m , n s n ,.. m w v . = __ x _J___

s.a.___ a _ s- . . m , _ u___ _ . :. _m .. . -a.'- <u- % f CPSES/EP (]) specifically the responsibility of the NRC. FEMA will send at least one individual to the EOF to coordinate the non-technical activities , with the NRC, CPSES and the State and local governments. 1.3.3.3 Department of Energy The DOE is the- third segment of the Federal response. They are responsible for coordinating Federal offsite radiological monitoring and assessment and for relaying this information to the NRC asse,ssment personnel at the site. The Department of Energy (DOE) has a regional Coordinating Office for Radiological Assistance located in Albuquerque, New Mexico. This agency is available on a 24 hour per-day basic to provide emergency radiological teams in support of the CPSES Emergency Organization. The Emergency Coordinator or the Recovery 11anager are the only two utility personnel at the site who may request DOE assistance. They will respond within 24 hours with resources that include:

a. Radiological assistance teams.; b. Communication equipment (including microwave capabilities).; c. Aircraft for airborne monitoring and transportation and mobile labs for surface monitoring.; d. Specialties (technical and administrative personnel not directly involved in field operations, such as information officers, clerical workers, etc.).; e. A DOE coordinator will be dispatched to the EOF to direct the DOE
resources pursuant to the requests of the Emergency Coordinator.

1.3.4 PRIVATE AGENCIES i 1.3.4.1 Squaw Creek Park, Inc.

Squaw Creek Park, Inc. (SCPI) operates and maintains Squaw Creek Park, a 470-acre recreation area adjacent to Squaw Creek reservoir and north of the station. The park and reservoir are owned by Texas Utilities.

I SCPI is responsible for controlling access to the park and reservoir. i The park and reservoir are accessible via a single public road from l l 1-24 REVISION 3 MAY 21,1982 i

_ , . . __ _ _ _ . . . . . . . _ _ _ _ _ . _ .,_ __ . _w

l l CPSES/EP b.,) s State Road 144. The letter of agreement details the responsibilities of SCPI during a Site Area or General Emergency at CPSES. SCPI is responsible for accountability and evacuation of the park and re se rvoir. 1.3.4.2 Westinghouse Electric Corporation The nuclear steam supply system at CPSES was supplied by Westinghouse Water Reactors Division (WRD). In its capacity as a supplier, Westinghouse can provide emergency assistance to CPSES on an around-the-clock basis. The Westinghouse Emergency Response Plan (Section 15, Appendix R) addresses the following:

1. Describes the WRD emergency response organization, its role, scope, functions and responsibilities, and how it is activated.

2. Identifies the key WRD individuals to be available in the early phase of an emergency response.

3. Defines the WRD interfaces with other involved parties.

4. Defines the WRD role in emergency news communications and its interaction with CPSES Public Information personnel and the news media.

I i L i i t it 1-25 REVISION 3

MAY 21,1982 4

i e i i r I wawms-ma m s ,6 m w +wm" - n - "Wn =' "

                                                                                                                           ~~ ~ W

              . .a m
                                                                                                                                                                                                          . l a

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                't                                                                                                                                                                                     &    -

f j ,k r . W ) CPSsS/sP TAGLE l.8 1 l k L STAFFING REQUIRE 8ENTS FOR EIG!aCENCIES f T Additions ! Within ?tta. Functlanal Area M Poettien Title On Shift 40 70 3 asation Operetton Assesenant of Operational Aspects Shif t Supervisor (SRO) 1 I Aset. Shif t Supervisor (SRO) 8 ( - Reactor Operatore (RO) 2 - ( Austitary Operatore 3 ; F Emetgency Direction and Centrol Shif t Supervisor (SRO)** I* I 4 > g Connunicatione , tbtify Station personnel and Member of shif t Operettg I* I I a maintain corveuntcettone Personnel e I Stetton Systers Engineering Technical Support Shif t Technical Advisor I ) Nuclear Engineer - t Electrical Engineer - t a hchanical Enginaer - t

Q Ilealth Phystetet -

1 Operatione Engineer - I Radiological Aeoessnest Stetton Surveye R.P. Techntelen 286* I I - Onent etry/Radiocheat stry Otan. 6 Envir. Technician - I l offette Surveys R.P. Techniciano - t 3 I J Onette Surveys R.P. Techniciana = 1 1 'l Dese Assesanente R.P. Engineer - 1 l 4 l l Systen Corrective Actions thinage Control Mechante !* I I I 3 Electrician 1* I l ] I&C Technician Austllary Operator ge 3 1

                                                                                                                                   ,                                        le                       !

Protective Actione Radiation Protection R.P. Tethatclan 28 2 2 l

a. Access Control '

b. Personnel Monitoring pl c. Dostmetry Fire fighting 58 Local a Support Rascue Operations and First Aid 2* tacal Support

!! Site Access Control Security, firefighting. Cuerde Per Security local l and Personnel Accountability Connunicatione, personnel Plan Support accountability k= TOTAL 10 18 16 !

May be provided by shif t personnet assigned other' functione.

                 **   Shift Supervisor serves in thle capacity ungt! rel*.eved by the Manager, Plant Operettone                                                                     REVISION 3                  !

or his alternate. MAY 21, 1982 .]

   ?             *** As a nietama, one Radiation Protection Technician shall be qualtfled to inttlate the post accident sampling and analyste process.                                                         ]

I J

yy - -. _ . - . . . , - - ..a . . . . . - - ~ . . . . ~ . ~ - . .-.~.-.......~.m. - - . _. _ _---- - _ - - - - e l

!          l   _ g.,                                                                                                                                  g, f6)                                                                                                                                   (d         j i

b CPSES/EP 1 f CRADED EMERCENCY ORGANIZATION RESPONSE i

;                                                                         Table 1.2                                                                             !

I

$                                       Notification of                                                                           Site Area l                                         Unusual Event                                         Alert                             or Ceneral t

l On Duty Personnel On Duty Personnel On Duty Personnel Off-Site Support TSC Activated TSC Activated [ Function OSC Activated (limited) OSC Fully Activated Off-Site Support EOF Activated ! Off-Site Support g _ .

Station Shift Supervisor Shift Supervisor Shift Supervisor f Operations Control Room Personnel Control Room Personnel Control Room Personnel Overall Shift Supervisor TSC Manager Emergency Coordinator ! Direction (Emergency Coord.) (Emergency coord.) EOF ' f Control

 ..             Communications    Control Room Personnel                            TSC Personnel                     Communications Coordinator                 '

.] Supplemented Control EOF Room Personnel ' Security Shift Supervisor / Security TSC Manager Security Supervisor EOF ( { w" Radiation Shift Supervisor TSC Health Physicist Radiation Protection Coor- ! Protection Radiation Protection Tech. RP Tech. dinator and personnel l EOF /TSC/OSC ] r Technical Shift Tech. Advisor Engineering Team Coordinator Engineering Team Coordinator ) Support Engineering Team Engineering Team ( i Damage Control Control Room, Radiation OSC Supervisor OSC Supervisor Protection Techs. 1 1 Fire Fighting Operations & Security Operations 5 Security Operations & Security

l Public Info. Shift Supervisor TSC Manager Public Inforuntion Coor- i

    ;                                                                                                                   dinator - Eb?                           g l

Logistics Shift Supervisor TSC Mar.ager Logistical Support Coor- 1 dinator - EOF e 4 REVISION 3 I MAY 21, 1982 i t 1

i 1 L L j j ld *) i l;;l.js!:j:( ;! l C N WKI 2 l AE B1 l l lll 8 UE , QRK 39 SCR A P 1 i J_ N 1 O , I1 _ S2 I VY _ EA T RM N _ E Y H G TFR ROE A N l l l l l g iI L P E E _ D SE ET I AS _ STRE AI OC XLPI EI RF N _ s o n TTOF n i Y E o t UCO LCC AN

i as t ve RE T a i l EC N DR lIIl g l g l 1L_ t u t t cl EE t i Al F S i O _ y ha ec c t F _ n e ge g ns _ r i n _ e d o _ m np E e . _ r P e R YN RRO o ecy AOI ETS _ f ac S LAS CL 1 lII lg l gllL_ e f n c a eg r e L YN UU1 9 AT CO NC! f r ne t r S CRR I OE NI R ETE EO RC _ e I m E NPT GAT t E n y C HPN RRN EEE _ i re A CUE ah F ESC MPC P R T EO l a opi rt E 1 E T _ m r mn

           /    1     N                                                        E I                                                         J o e S     e                                                     TA NS

_ 1 T E r L E S u A _ g N SMC P i O ATI XRL 8 i3 I g $ill C F I T EAB 1_ C TPU EP _ N l i f D F _ _ T NH _ _ ET SHL ATA lll l g l g l l XRE EAH A TP EF DO _ L .e L ft cl EY Y f pna VTC T ieat L RNO N rDl i i, ' O EUE U e up R L MO O heb s T A OC C Sr mo N NT S iAH OH ORR F CO O I OE TPT IJ _ SR APN RUE E S P ESC F O Tl lg l g I i L_ C I' _

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ll Il lli_ e}l V yIkQ

1 COMANCHE PEAK STEAM ELECTRIC STATK)N TEXAS UTE.fTES GOERATUG COMPNtf r

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I lal Isl Irl -Da ll==Il al [X11=.llel l lal l=-I l = l- l-l l-l 1 c [ l=1 l=! . o a ' p COMANCHE PEAK S.E.S. !i aun nu > lal I-l l-I I UNITS I and 2 i 4 station oecant:arlon [i REVISION 3 HAY 21, 1982 FKiURE },7 "y

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                          %.)                                                                                                                                                          ,                 Q 1 - .. - . . . . . . _ . . . . .        . . _ . . . . . . . .             . _ , . .   . . . . _ . . _ _ . , .          , . . . _ _ .            ._,    .   ._          __                                                  J

o e E. CPSES/EP l ;

                              . .                         .. .                                                              TUGCO NUCLEAR ORGANIZATION FIGURE 1.3 q

h EXECUTIVE VICE PRESIDENT

 .h                                                                                                                                                                               AND CENERAL MANAGER 1

VICE PRESIDENT

!                                                                                                                                                                              NUCLEAR
.i h.

i

.(

l i ENGINEERENC AND MANAGER HEALTH PHYSICS MANAGER ADMINISTRATIVE NUCLEAR OPERATIONS SUPERVISOR QUALITY ASSURANCE SERVICE .I ii b e l s 1 MANAGER [] PIANT OPERATIONS COORDINATOR SUPERINTENDENT DIRECTOR LEAD START UP lg PUBLIC INFORMATION OPERATIONS SUPPORT NUCLEAM TRAININC EHCINEER f L REVISION 3 MAf 21.1982 j FIGURE 1.3 i 4 ! I I l

i I' o

,                      O                                                                                                                                                                                                                   U)           V I

CPSES/t* ! p I

      ,                                                                                            COMANCHE PEAK STEAM ELECTRIC STATION                                                                                                                 !

t EMERGENCY ORGANIZATION nCune i.. r j r 7

I I l l "*;o""' CORPORATE l I f ! OFFICES l t_- - - ' --_____ a [

4 l e - sener EMERGENCY OPERATIONS !g t g Coordinator i FACILITY . i ; i l I i I I i j i I I I I I i . l Fublic Logistical Radiation

-t                                    g  Conseunications                               Inf ormation                           Security                                          Suppor t                 Protectica                      j g    Coordinator                                Coordina tor                           Supervisor                                       Coordinator                Coordinator                     l i

l l . l L -- __.___ _, l : i 7 l l l l ' l rechnical l l Onsite Offsite i l

,(                                                                                                                                                 Support                                                                               !

l g Radialogical Radiological

l                                                                                             I                                                  Center                 l          l      Coordinator                Coordinator       !              I{

s Manarer l l { I : - I " "

-!                                                                                          ,     1 i

iw i I- g I 4 t-3 CONTROL ROOM iu l I l

!)      i I             jj                  i                                   l                                I            j       i                I         OPERATIONAL    i E

l[

]                                  $niet                                  Smirt                           rec 6mic.i                              rechnicai                     r..ineerin.        I        i          o,eratio !        SUPPORT l      [
~       i                 1 - unic.i Advisor Su,               .isor lli
                                                                                              ,g Su,, ort C.nt -

tiealth Physicist S.,,- Advisor c nt- re Coordinator j i su,,urt Cent" Supervisor CENTER I i g l

                                                                                              '                                                                                                                                     ~

1 I d- - -- _=, 11 I j i 3 I ! L i _ i i TECHNICAL Engineerins v..e g i I I f l l l l gl Nuclear Engineer l and Damage i'

 '      '                                                                                                                                                            """"*"""                        '        ca"' " '

g l Assistant II SUPPORT Electrical Engineer l i c'"' s ! i ll ;. Swirt .eacio, A ini r ii CENTER "*"""""

                                                                                                                                                                                                   !        '                                       g i

Supervisor Operators Operators I r j g

   ;     g                                                                                                                                                                                                  g         Asiational                   -l I                                                                                                                                                                                                            P*'ato n
   )      L_______         _ _ _ _
                                                   - - - -                                                             e i                                                                                   i l

REVISION 3 l MAf 21.1962 g , I a L FIGURE I.4 h ,b h 3 } 4 i .' k p k t

[ g CPSES/EP

 !   G)

I l 2.0 EMERGENCY CLASSIFICATION SYSTEM Emergency classifications are those in which situations are occuring which cause or threaten to cause radiological hazards affecting the

 !                 health and safety of employees or the public or resulting in damage to j                 property. These situations range from those which result in no effect g                 to those which result in severe consequences to the public. These f                 situatious have been categorized into four Emergency Action Levels.

2.1 EMERGENCY ACTION LEVELS l The four classes of Emergency Action Levels are:

3 a. Notification of Unusual Event. I a 4 b. Alert. 3 4 c. Site Area Emergency. j d. General Emergency. 1 1 The first two classes are designed to provide early notification to g offsite agencies of minor events which might lead to more serious consequences due to incorrect personnel actions or equipment failure. The Site Area Emergency class includes conditions in which significant

             ,     releases are occuring or are expected to occur, but a core meltdown 4                   situation is not indicated. The General Emergency class is the situation in which actual or imminent core degradation or melting occurs with the potential for loss of containment.               A gradation of responses is provided to assure prompt action whether the seriousness of the event intensifies or diminishes.

1 The following tables list examples of initiating parameters for the ) Emergency Action Levels. These tables provide guidance for the ] development of the implementing procedure, EPP-201 " Assessment of ] Emergency Action Levels and* Pian Activation". This procedure details j the paraneters for determining emergency action level and prescribes y the necessary actions to set the Emergency Response Program in motion. 4 2.1.1 NOTIFICATION OF UNUSUAL EVENT 4 This is the lowest category of the Emergency Action Levels which j requires offsite notification. In this category are unusual events 1 which have occurred or are in progress which indicate a potential degradation of the level of safety of the plant. A general ) h 2-1 h l REVISION 3 MAY 21,1982 w u rw&&=rsg _ , , . ". 7m~w"*e -- --~ _

                                                         .~w     *"    MMMMyn,        .2     ._--   ,"w         7 , .- ,. ; -

1 4

 .i 3

r. 3 J- . rj CPSES/EP y i description of this category of events is found in Table 2.1 and j examples of initiating conditions are in Table 2.2. - 1 1 J i 4 h

',I '

4 i v 1 J d 1 J i 1, '1 l .I f L i 1 4 k i' ) (j

4 Il r .

4 1

2-2 Q 4 1 2 REVISION 3

   ]      MAY 21,1982

,s

   * ~M     . %-m-        ;- _ _ _ . _ _ _ _ _ _ _.a_

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CPSES/EP f% TABLE 2.1 NOTIFICATION OF UNUSUAL EVENT Description Actions Unusual events are in process 1. Promptly inform NRC and DPS or have occured which indicate in W' a co of nature of the a potential degradation of the unusual conditions. level of safety of the plant. Purpose 2. Augment on-shift resources as needed. Purpose of offsite notification 3. Assess and respond. is to (1) assure that the first step in any response later found 4. Escalate to a more severe to be necessary has been carried class. out, (2) provide current in-formation on unusual events, cg; and (3) provide a periodic . unscheduled test of the of f- Close out with verbal summary site communication link. to the NRC and to DPS; follow-ed by written stanmary Release Potential within 24 hours. No releases of radioactive material requiring offsite response or monitoring are expected unless futher degradation of safety systems occurs. 2-3 (1) REVISION 3 MAY 21, 1982 _., _m,

                         , , _ _ _              . - _. ._ _ _            _. z,

_.,.m _ __ . _. .

_ _____ - - - _ - _ - - _ _ _ - - _ . - _ _ . . . , . >---m- ---

I CPSES/EP TABLE 2.2 b (SHEET 1 0F 4) INITIATING CONDITIONS: NOTIFICATION OF UNUSUAL EVENT Abnormal Condition Examples of Initiating Parameter

1. Any high energy line break Any advertent Safety Injection

;                             large enough to cause an                         Actuation signal caused by a ECCS initiation.                                 steamline break, feedwater line break, or a loss of coolant accident or any inadvertent Safety Injection.

2. Radioactive ef fluent Exceeding Radiological release to the environ- Effluent Technical Specifi-ment above allowable levels. cations (T.S.):

   !                                                                             T.S. 3/4.11.1 for Liquid Effluents.

T.S. 3/4.11.2 for Gaseous Effluents.

3. Fuel degradation indication. A. Analysis of Reactor Coolant sample showing abnor:nally high gamma activity and abnor-j mally high fission product activity. T.S.3/4.4.8 B. Abnormally high reading from failed fuel monitor.

4. Abnormal coolant tempera- A. Exceeding the pressure, teep-ture and/or pressure or erature limits of T.S.3/4.4.9.

abnormal fuel temperatures. B. Unexplained high readings from l Incore thermocouples. i

5. High primary system Exceeding primary system leak rate. Technical Specification

, leak rate. Applicable modes 1, 2, 3, 4. (T.S. 3/4.4.6). ? ) I - i - e I r 2-4 ,] a I REVISION 3 MAY 21,1982

i

     -~%     -__ __
                        , ..m p - w.- ,w r-- v;,,,m             & - n w z-            -g
                                                                                       . s j.m-         .-_ . ag_ M e a.-

m..--..__......~.-..~ . - - - _ - _ = . - - - - - - = ~ ~ m i

CPSES/EP i Ih TABLE 2.2 (SHEET 2 0F 4)

6. Failure of a pressurizer A. From valve position indi-i or steam generator safety cation in Control Room.

i valve to close cn; a B. Inferred from leak failure of a pressurizer detection methods. or steam generator power ! operated relief valve to close that cannot be h isolated. l l 7. Complete loss of offsite A. Station blackout with power or loss of onsite emergency diesel generators j AC power capability. available.

B. Loss of standby AC power

, with offsite power still i available. )

8. Loss of containment See T.S. 3/4.6.1 Primary integrity requiring shut- Containment Integrity.

down.

9. Loss of engineered safety Specific attention should be feature or fire protection given to the following techni-l, system function requiring cal specifications:

shutdown. T.S. 3/4.3.2 ESF Actuation System Instrumentation. ' T.S. 3/4.5 Emergency Core Cooling Systems. 3 T.S. 3/4.6 Containment Systems. T.S. 3/4.7.1 Section 3.7.1.2 ' Auxiliary Feedwater System. T.S. 3/4.7.1 Section 3.7.1.3 Condensate Storage Tank. l i T.S. 3/4.7.4 Service Water System. l ? T.S. 3/4.7.11 Fire Suppression. 4

10. Fire lasting more than j 10 minutes within the boundaries of the

~ j protected area and

not threatening safety r systems.

b I l .g 2 i, *lb [ REVISION 3 MAY 21,1982

            ,,..-yv-rr.--~~~             ~c ~ : .-~ mmm'~ ~                 . - - ." ?T**- -

x- ==c -

'~

M ml

  ; + w.w  -.u-       .mm           :--          - - . .  ~       ~ . , > - .      .~                              --

I 1 l CPSES/EP I

                                                                                                               ;]w l

TABLE 2.2 (SHEET 3 0F 4)

11. Indications or alarms Loss of instrumentation on process or radio- requiring shutdown by logical instrumentation Technical Specifications not functional in the 3/4.3 Instrumentation.

control room to an ex-tent requiring plant shutdown, or other significant loss of assessment or communi-cation capability.

 !              12. Security threat.                     A. Bomb threat.

B. Group attempting to trespass.

13. Natural phenomenon A. Any earthquake indicated being experienced or by seismic instrumenta-projected beyond usual tion.

levels.

B. 50 year flood.

C. Water level in SSI dropping and approaching the low water level. D. Any tornado observed approaching plant site.

14. Other hazards being A. Aircraft crash onsite or experienced or projected. unusual aircraft activity over facility.

B. Train derailment onsite or nearsite posing safety threat 1 to the plant or employees. C. Near or onsite explosion. j D. Near or onsite toxic or flammable gas release. 3 E. Spill of a significant ! quantity of hazardous i material. No significant i release to the environment 4 and not affecting safety

systems.

3 i e 1 2-6 ())

REVISION 3 i MAY 21,1982 L

, n - .,- , , ,= -m-=n - - w -m v n m m - - - ~~ ~e ~ # ~ " ---- : t-

CPSES/EP i l{} TABLE 2.2 (SHEET 4 0F 4)

15. Other plant conditions As determined by the Station exist that warrant Operations Review Committee

  '                 increased awareness on                      or the Manager, Nuclear the part of the State                      Operations, his designated and/or local offsite                        alternate, or by Technical authorities or require                      Specification requirements.

plant shutdown or involve other than normal controlled shutdown.

16. Transportation of a contaminated injured individual from the site to an offsite hospital.

I i I e l 1 i l f s l = i-2-7 l b 4 REVISION 3 i MAY 21,1982

    ~     'Y WW         m W, 4
                                 ~ vw'   --m-   " -=            W                  W

f wf v--- - ,- W ,

3

_ _ ... _ - - . _ _ _ . = = _ - - - - - - ~ . - - . - - - -.m - -

CPSES/EP 2.1.2 ALERT In this action level are events which have occured or are in progress which involve an actual or potentially substantial degradation of the

,                          level of safety of the plant.             These events are serious enough to require activation of the TSC.

i Prompt notification of DPS of the plant condition is essential, with i possible notification also to local authorities. A description of this action level is in Table 2.3, with examples of initiating conditions in Table 2.4. ) N e i ? 1 h f l 4 I i p i ( 4 l r 1 i i i i 2-8 h r REVISION 3

 ,             MAY 21,1982

(.__.,,..---m_,- - - - , - . - - - - m mm - -

                                                                                                   - - - = -        -

   ~.c...~.-                --                              --         ---
                                                                                                    -~:~.:---

CPSES/EP TABLE 2.3

         ', -]

ALERT Description Actions Events are in process or 1. Promptly inform NRC, DPS in have occured which involve an Waco, and possibly local actual or potentially sub- authorities of the Alert. stantial degradation of the level of safety of the plant.

2. Augment resources by acti-vating Technical Support Center.

Purpose 3. Assess and respond. Purpose of offsite alert is to (1) assure that emergency 4. Dispatch onsite monitoring personnel are readily avail- teams and associated able to respond if situation communications. becomes more serious or to perform confirmatory radia- 5. Provide periodic plant status tion monitoring if required, updates to offsite (2) provide offsite authori- authorities. ties current status information, and (3) 6. Provide periodic meteoro-provide possible unsche- logical assessments to offsite duled tests of response authorities and, if any center activation. releases are occuring, dose estimates for actual Release Potential releases. Limited releases of up to 7. Escalate to a more severe 10 curies of I-131 equivalent class. to 104 curies of Xe-133 equivalent. _or Close out by verbal summary to offsite authorities i followed by written summary within 8 hours of

                                                     .                     close-out or class reduction.

! 2-9 s '. REVISION 3 MAY 21,1982

 .            . - . . _ . -    m.m.,_.m...--_.._._,                     m.          m  ~ _         _ -. -     _.

              . . _ _      _ _ _ _ _ . _ _         -_ _ , . . _ _ - - - -                m.-..-        -_ --   mr-- n - - , - -]

CPSES/EP TABLE 2.4 (SHEET 1 0F 4) INITIATING CONDITIONS: ALERT ! Abnormal Conditions Examples of Initiating Parameter

1. Severe failure of fuel A. A reactor coolant sample indi-cladding. cating very high gamma activity and very high fission product activity, exceeding Technical Specification limits. T.S. 3.4.8.

B. Very high reading from the failed fuel monitor.

2. Steam generator A. Safety injection with high tube failure with steam generator blowdown loss of offsite power. activity or condenser vacuum pump exhaust high radiation alarm.

B. Station blackout with automatic start of emergency diesel generators.

3. Gross failure of Primary to secondary leak steam generator tubes. resulting in high charging rate with decreasing pressurizer level.

4. Steam line break with Safety injection with steam greater than 10 gpm line break indication coin-primary to secondary cident with high activity in leak rate or with MSIV steam generator blowdown or malfunction. high condenser vacuum pump exhaust radiation alarm.

5. Primary coolant leak A. High Containment Activity.

rate greater than B. Rising containment sump level 50 gpm. not attributed to other sources. C. Abnormally high charging requirements or large makeup water requirements. 2-10 O REVISION 3 MAY 21,1982 n - ng.-.- ,. n.- -.=.- . - nwr-e,-- -m -nm. w - .--n_~-__

7.- CPSES/EP TABLE 1 (SHEET 2 0F 4) i

       ,3
       -d                 6.        High radiation levels                  A. Large increase (several                '

or high airborne con- decades above nomal) in tamination which area radiation monitor - indicate a severe readings. degradation in the B. High airborne contami-l

control of radio- nation indicated by high j active materials. reading on P.I.G. !

3 monitors. . i j 7. Loss of offsite power Station blackout wita i and loss of onsite emergency diesel AC power for less generators failure to chan 15 minutes. start.

8. Loss of all vital onsite DC voltage indicates DC power for less than low.

l 15 minutes.

9. Loss of Reactor Coolant Loss of flow reactor trip flow leading to fuel failure. with subsequent high fission l product activity in Reactor i Coolant sample.

10. Loss of functions Loss of Auxiliary Feedwater l needed for plant cold System, two or more steam l

[ shutdown. generators inoperable, or

inability to borate to cold shutdown. Failure of i both trains of ECCS.: 11. Failure of the A. Operation exceeding automatic reactor protection reactor trip setpoints.

system to initiate B. Any anticipated transient l and complete a without trip event. trip which brings the reactor suberitical. f 12. Spent fuel handling Hign radiation levels accident with release indicated by containment of radioactivity to and fuel building area i containment or the Fuel radiation monitors. Building. 2-11 l q l ) REVISION 3 .. MAY 21, 1982 m r2 7.c . e.wr_ - r-mrr_- , m:- m m - e_ sa=--- .

-n

  ; . . ..      . ~ . - ---           .
                                           - - .-c        .
                                                                                 -.w-      ,_ a.=        ..w:  --
                                                                                                                      -=

I

)                                                                  CPSES/EP i

i l TABLE 2.4 (SHEET 3 0F 4) f 13. Fire potentially Fire in cable spreading j affecting safety systems. room. 1 l 14. All alarms (annun-ciators) lost for less than 15 minutes. l 15. Radiological effluents A. Determined by very high greater than 10 times reading on effluent

;                           Technical Specifications                         monitors.

j instantaneous limits. B. Error found on pre-release j sample or analysis. j C. Radiological Technical i Specifications: T.S. 3/4.11.1 or T.S. 3/4 11.2. j 16. Ongoing Security il compromise. I

17. Severe natural A. An earthquake greater than phenomena being exper- on Operating Basis Earthquake.

ienced or projected. B. Any flood in the Safe Shutdown Impoundment (SSI). C. Any tornado striking the facility. } D. Low water in the SSI.

18. Other hazards being A. Aircraft crash into facility

] experienced or projected. buildings or structures. B. Missile impact from whatever source causing damage to facility structures. 4 C. Known explosion damage to 3 facility affecting plant 1 operation. ]' D. Entry into facility environs of toxic or flammable gases. a E. Main turbine generator i failure causing damage } , to buildings or structures. t F. Significant release of hazar-S dous material to the environ-j ment of spill affecting l safety systems. s i a ? 2-12 O i d 1 l i! a , 1 i i Q a ; l i h, ! t l!., i k , 4 - l a t d i li 2-14 0, j IN i ) 1 9 ol !i ! o p REVISION 3 j MAY 21, 1982 ' I z1== .===== = . = . ==:a . a= = ~ ~ ~ m -

~~~- = = =d
_ m ana w -x.u.: - e-w:. .- -.an - . _ . . . - - - - _ . - . - . - - - - - CFSES/EP j q b,s, TABLE 2.5 (SHEET 1 0F 2) SITE AREA EMERGENCY ~ l Description Actions f Events are in process or 1. Promptly inform NRC, DPS l have occurred which involve and/or county EOC's of Site [ actual or potential major . Area Emergency status and failures of plant functions reason for emergency. needed for protection of the public.
2. Augment resources by Purpose activating Technical Support Center, Purpose of the Site Area Operational Support Center, Emergency warning is to. (1) and Emergency ;
assure that response centers Operations Facility. I are manned, (2) assure that l monitoring teams are dis- 3. Assess and respond. l patched, (3) assure that personnel required for 4. Dispatch onsite and l evacuation of near-site offsite monitoring areas are at duty stations teams and associated l if situation becomes more communications.
serious, (4) provide current information for and consulta- 5. Provide a dedicated tion with offsite authorities individual for plant l and public, and (5) provide status updates to of fsite l possible unscheduled test authorities and periodic of response capabilities. press briefings.
Release Potential ! Releases of up to 1000 Ci 6. Make senior technical and of I-131 equivalent or up management staff onsite l to 106 Ci of Xe-133 available for consultation equivalent. with NRC and State on a periodic basis. l l 2-15 l
.)
l REVISION 3 MAY 21,1982 I _.m . _ _ ._ m__m_ .s , m- , _. _ % ~ - _
p : : --- x - -- - .:_=a. ::;;-x = .,w.umaw== - u.x- ww= -- ar-- w _nr CPSES/EP i TABLE 2.5 (SHEET 2 0F 2) O l g 7. Provide meteorological and dose esticates to offsite authorities for actual 4 releases.
8. Provide release and dose pro-jections based on available plant condition information
! and foreseeable contingencies. k
9. Escalate to General Emergency class.
or Close out or recommend reduc-r tion in emergency class by briefing of offsite authorities at EOF followed by written summary within 8 hours of close-out or class
reduction.
9 . i r . I l t 2-16 i I ! 1
; O !
i f REVISION 3 MAY 21,1982 1 !
, m , mn.e n.---,- . c - ,-- mm y2 p ampxm_~ m,m .e
CPSES/EP TABLE 2.6 (SHEET 1 0F 4) [. } INITIATING CONDITIONS: SITE AREA EMERGENCY Abnormal Condition Examples of Initiating Parameters
1. Known loss of coolant High charging flow rate with accident greater than decreasing pressurizer charging pumps capacity. level.
! 2. Degraded core with A. Core subcooling monitor l possible loss of indicates core tempera-l coolable geometry. ture at or above j saturation. j B. RCS activity indicates massive fuel failure. C. Containment area radiation monitors reading very high levels. i l 1
3. Gross failure of Safety injection actuation steam generator with high secondary tubes with loss of activity levels, coin-offsite power. cident with station blackout resulting in auto start of emergency diesel generators.

4. Steam line break with Steam line break resulting greater than 50 gpm in Safety Injection primary to secondary Actuation, coincident with leakage and indica- high activity levels in tion of fuel damage. the steam generator and high fission product
, activity present in steam generator and the Reactor Coolant System.
5. Loss of offsite AC Station blackout and power and loss of failure of emergency onsite AC power diesel generators to l for more than 15 start.
! minutes. . i f 2-17 , t ) l (S) , r REVISION 3 M AY 21,1982 l l l '
m. . . n - - x - --
-.. -__ _ =_ _2
-: . 2 . =='- = a. z .w ;c.r ..--w = -
w- w. m i i W li CPSES/EP a 'i . 1 TABLE 2.6 (SHEET 2 0F 4) O
6. Loss of all vital Low DC voltage onsite DC power indication.
d for more than 15 l minutes. I i 7. Loss of functions A. Inability to trip the I needed for plant control rods. ) hot shutdown. B. Loss of decay heat f removal capability at r: hot shutdown. ,j 8. Major damage to spent A. Object damages spent fuel n fuel in containment or spent fuel assembly $ or fuel building. dropped,,resulting in d damage to fuel cladding. j B. Loss of water in spent j fuel pool below fuel 1 level. 1 C. High area radiation ] readings in containment 'i and fuel building. 3
}
4 9. Fire affecting safety Actual loss of a safety
j ' systems. train or train-related 1 component due to a fire.
1 10. All alarms (annun-j eiators) lost for more 1 than 15 minutes and plant ] is not in cold shutdown .l or a plant transient is initiated while all alarms lost. l s
)
k, 1 i j 2-18 i 1 C REVISION 3 MAY 21,1982
, , , , , . - - . . . - - -,-.-.- ...- , _ _ -.- ~ ~- _ -
CPSES/EP TABLE 2.6 (SHEET 3 0F 4) eb
?
11. Dose rates at the site Dose rates may be determined boundary for adverse several ways:
meteorological con-ditions are at levels A. Using effluent monitor corresponding to readings and meteoro-50 mr/hr for 1/2 hour logical parameters from cy greater than 500 the Radiation Monitoring or/hr W.B. for two System Computer. minutes (or five times B. Measuring containment these levels to the activity and calcu-thyroid). lating containment leak rate for the present containment pressure. C. Measuring dose rates a: the site boundary using fixed dosimeters or portable field measure-ment devices.
12. Imminent loss of physical control of the plant.

13. Severe natural pheno- A. Earthquake greater than mena being experienced a Safe Shutdown Earthquake.
or projected with B. Flood, or SSI low water plant not in cold level beyond design shutdown. levels or failure of vital equipment at lower levels. C. Winds in excess of design levels.
14. Other hazards being A. Aircraft crash affecting experienced or pro- vital structures by jected with plant not impact or fire.
in cold shutdown. B. Severe damage to safe shutdown equipment from missiles er explosion. C. Entry of toxic or flammable gases into ) vital areas. i i l REVISION 3 2-19 MAY 21,1982
- = , - . = - ~ .- = ~ _ .~-~. n . --- _ .. -
a _ - m i t i CPSES/EP 1 TABLE 2.6 (SHEET 4 0F 4) O
15. Other plant conditions exist. chat warrant activation of emer-gency centers and monitoring teams and a precautionary public notification.

16. Evacuation of Control Room and control of shutdown systems not established from remote shutdown panel or local stations in 15 minutes.
I i ( i l O c r i i REVISION 3 l MAY 21,1982 2-20 l gg,. ,_- --,. - ,, -~ ,~ , . .. . -- - --, mm x a a . - ==w ns - mo w-
p.s. a. . __ _-. . .-. - - - . . - . . .~ . - . . _ - . - - - . - -, I l CPSES/EP '1 g 2.1.4 GENERAL EMERGENCY f This is the highest class of Emergency Action Level and involves actual or imminent substantial core degradation or meltdown with a potential for loss of containment integrity. The purpose of the General Emergency is to initiate predetermined protective actions for the public and to continually appraise the emergency condition with appropriate responses. A description of this action level with appropriate responses is in ,. Table 2.7, with examples of the initiating conditions in Table 2.8. I l i 1 . I l I i l f i i ! l ! l ! l I i i l I I j b- , REVISION 3 ; 2-21 MAY 21,1982
- --em_ -- . n_-------. - - ~ - . . - - - - -
- _ - . . ~ ._ ._ _ - , _ __ _
l CPSES/EP' I i k I I TABLE 2.7 (SHEET 1 0F 2) p... GENERAL EMERGENCY Description Actions l Events are in process or have 1. Promptly inform NRC, DPS in Waco i occurred which involve actual and county EOC's of General l or imminent substantial core Emergency status and reason for ! degradation or melting with emergency. (Parallel notification f
. po tential for loss of con-of NRC/DPS/ COUNTY).
t tainment integrity. l Purpose 2. Augment resources by activating Technical Support Center, Purpose of the General Emergency Operational Support warning is to (1) initiate pre- Center and Emergency determined protective actions Operations Facility.
!a for public, (2) provide ) continuous assessment of informa- 3. Assess and respond.
tion from onsite and offsite measurements, (3) initiate 4. Dispatch onsite and offsite + l additional measures as indi- monitoring teams and asso- I cated by event releases or ciated communications.
?
potential releases, and (4) ! provide current information for S. Provide a dedicated individual and consultation with offsite for plant status updates to } authorities and public. offsite authorities and i periodic press briefings. I Release Potential 1 Releases of more than 1000 Ci l 3 of I-131 equivalent or more 6. Make senior technical and
& than 106 Ci of Xe-133 management staff onsite j equivalent. <
available for consultation I with NRC and State on a periodic basis. 3 a
7. Provide meteorological and dose estimates to offsite authorities for actual releases.
7 L .
-3 I! l
1 i.
t b 1
} REVISION 3 t MAY 21, 1982 2-22 p
__ a - # ^
.-~:..__,_,.n,_._n..n.__._.._,,,.
7___ n: _ - . .. i i I CPSES/EP l
+7 7 i \ ; .) TABLE 2.7 (SHEET 2 0F 2) -l I
8. Provide release and dose projections based on available plant condition information and foreseeable contingencies. 6 i

9. Close out or recommend reduction l of emergency class by briefing i of offsite authorities at the EOF and by phone followed l i
by written summary within 8 ' hours of close-out or class ! reduc tion. ' t l h E [ h i I i r [ i l i l t l REVISION 3 MAY 21, 1982 2-23 m .~. . - . _ n, . _: :- ,
= = ~ _ - - _ _ - . _ _ _ -_:_ ~-- -~-- -
. . _ _ m._ _mm.,_% -
CPSES/EP l TABLE 2.8 (SHEET 1 0F 2) INITIATING CONDITIONS: GENERAL EMERGENCY Abnormal Condition Examples of Initiating Parameter
1. Dose rates at the site Dose rates may be determined !
j boundary under actual by several ways:
meteorological condi- A. Using ef fluent monitor
' tions are at levels readings and meteoro-corresponding to logical system parameters - l 1 rm/hr W.B. or from the Radiatior Moni-i 5 rem /hr to the toring System Computer. thyroid. B. Measuring containment activity levels an( calculating contain. 2t leak rate for the pre-sent containment ) pressure. ! C. Measuring dose rates at l site boundary using fixed j dosimeters or portable field measurement j devices.
2. Loss of fission Massive fuel clad
$ product barriers with a failure from a loss of
potential loss of the coolant accident, and a j final barrier. high potential for a breach 1
of containment. l 3. Loss of physical control ) of the facility. i , i 1 l 1 l I i G ; I I l i
REVISION 3 ,

MAY 21,1982 2-24 i I
=
__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - - - ta - - - - - - ~ '
_ _n.-a-__..- - . - - ~ - - - . - - ~ . . ~ _ ._.- ----- _ ~ CPSES/EP g rg TABLE 2.8 (SHEET 2 0F 2) VU
4. Other plant conditions Some Example Sequences are:
exist, from whatever A. LOCA's with failure source, that make of ECCS to perform release of large leading to severe amounts of radio- core degradation or melt. activity in a short Ulttsate failure of con-period possible. tainment possible for melt sequences. B. Transient initiated by loss of feedwater and condensate systems followed by failure of auxiliary feedwater system for extended period. Core melting possible in several hours. Ultimate failure of containment possible. C. Transient requiring operation of shutdown systems with failure to trip. Core damage possible. Additional failure of core cooling and makeup systems could lead to core melt. D. Failure of offsite and onsite a power along with total loss of emergency feedwater makeup capability for several hours. May lead to core melt and possible failure of containment.
/')l u
REVISION 3 2-25 MAY 21,1982 \
~ ~ ~r -~ . . , _x=___ -_x:m:_=-_"'"_~~~~_~~_~~'^~ ' "~ ~ ~ ~ ~ ' ~ ' ' ~ '
n -- - - -. _ _ _
- . - ~ .- , --
CPSES/EP O v 3.0 NOTIFICATION METHODS AND PROCEDURES A procedure EPP-203, " Emergency Notification and Communications" i delineates the notification criteria for each Emergency Action Level, the time constraints on initial and close-out information messages, the methodology for notifying emergency response personnel and the i details on call back verification of telephone and radio communications. This procedure also contains pre-determined emergency g notification messages, which are intended for the supporting emergency 4 response organizations, based on items listed below. Public notification is accomplished using an outdoor alerting system a consisting of forty (40) acoustical devices rated at 125 decibels (at 4 100 feet) and a warning system that utilizes the Emergency Brocdcast System. Texas Utilities retains ownership of and maintains the outdoor system; however, each county is responsible for activatir; the portion of the system that is within their jurisdiction and for g ensuring that EBS has the proper message to broadcast. All forty 5 devices can be activated simultaneously from either county's Emergency d Operations Center. This system complies with NUREG 0654, Appendix 3. { Prepared messages intended for the public for information purposes, j are attached to the Procedure EPP-212, " Release of Emergency Related e Information to the Public". 1 ?
3.1 NOTIFICATION MESSAGES f
I Notification messages fall into two categories: inital and follow-up. I Initial messages provide a mininum of information and are intended to
! be used one time: when communications with the response organizations
[ are initiated. The follow-up messages are to be used for subsequent information exchange and to provide sufficient information to these organizations so they can accurately assess conditions at the site. 3.1.1 INITIAL NOTIFICATION MESSAGES Initial Notification Messages shall contain information about the class of emergency, whether a release is taking place, potentially p affected population and areas and whether protective measures re d necessary. a l 3-1 I F G
REVISION 3 MAY 21,1982 u _m._ _ __ _ _- -_ _
___m.~.m~.m._. .--.m . . . ~ mm - : mm - '-=-_;.:.:.w = ~ m w.u. ;;_ r 1 I CPSES/EP a 3.1.2 O FOLLOW-UP EMERGENCY MESSAGES I ( l Follow-up Emergency Messages shall contain the following information ; j if it is known and appropriate: ' l
! k
a. location and incident and name and telephone number (or j communications channel identification) of caller; i b. date/ tine of incident; I
i i c. class of emergency; h' j d. type of actual or projected release (airborne, waterborne, , surface spill), and estimated duration / impact times; I j e. estimate of quantity of radioactive material released or being 1 released and the points and height of releases; e f. chemical and physical form of released material, including { estimates of the relative quantities and concentration of noble j gases, iodines and particulates;
1 g. meteorological conditions at appropriate levels (wind speed,
] direction (to and from), indicator of stability, precipitation, if any); I h. actual or projected dose rates at site boundary; projected < s integrated dose at site boundary; u
. i. projected dose rates and integrated dose at the projected peak h and at 2, 5 and 10 miles, including sector (s) affected; I
j. estimate of any surface radioactive contamination inplant, onsite or offsite;
k. licensee emergency response actions underway;

1. recommended emergency actions, including protective measures; e

m. request for any needed onsite support by offsite organizatioas; H and -
H
n. prognosis for worsening or termination of event based on plant
{ information . b 0 y 3-2 h 1 ) REVISION 3 MAY 21,1982 kWMe**?W u _ y.^% , _; w - -- - . *" '~***?"'"* - A MAN - - _ - N"ETI- _ M
(.. CPSES/EP b 4.0 EMERGENCY COMMUNICATIONS A comprehensive communications' system is provided to ensure reliable intraplant communications, plant to offsite telephone and carrier communications, and offsite emergency communications capabilities with i public safety agencies. Effective communication between personnel during plant startup, operation, shutdown, refueling, and maintenance activities is provided by the use of private automatic branch exchange (PBK) telephone, sound powered telephone, public address, or two-way radio systems. Figure 4.1 illustrates the CPSES communication ne two rk. A sound-powered telephone system, independent of all other systems and external power sources, is provided to serve two purposes: to provide communications in critical areas and serve as a backup to the public address system in these areas and to provide uninterruptible communication channels for maintenance, calibration, testing, and refueling activities. These diverse means of communication are independent tc prevent the loss of all systems as a result of a single failure. An emergency alarm system is installed which provides a i unique alarm signal to ensure personnel evacuation. l The precedure, EPP-203, " Emergency Notification and Communication 2", provides instructions for the initial notification of all necessary personnel and agencies who are to respond to or be cognizant of an emergency at CPSES. Included are personnel and agency call lists, { instructions for telephone operators and notification message formats to ensure accurate information is given to the support agencies. l l Communication responsibilities for the organizations are described in Table 4.1, " Emergency Communication Responsibilities." This table lists the titles of the individuals who have the primary responsibility for emergency communications. Individuals with responsibility for implementing communications are listed, as applicable. 4.1 SYSTEM DESCRIPTION The following systems comprise the intraplant and plant-to-offsite communication systems for both units. 4-1 i REVISION 3 MAY 21, 1982 I m, gy ..,~--n--y--.-..~ - - - . ~ . . - - . -
-~. ---. ._ , _
yy. _
ma.mu a

x- . . . < - ~ - - -= ,-~_m-u...-- --
h 3 CPSES/EP 4.1.1 PUBLIC ADDRESS SYSTEM s i 2 The intraplant communication system (public address system) provides l two separate and independent channels of communication, namely page } and party linec. The page-party line loud speakers are powered by i individual amplifiers, and power to this system is supplied from a l source which is available upon loss of offsite power. ! The system layout- permits communication between the Control Room and ) all plant areas and buildings of the two units. The system also ] permits two-way communication between two or more locations. Speakers and microphone handsets are installed at locations vital to the operation of the plant and the safety of personnel. The voice paging channel output is audible over the expected noise levels under both normal and accident conditions. Five separate and independent party lines are provided to permit communication between handsets only, thereby making the page channel available to others. All five party lines are available at all - handset : ations, except those in elevators where only one party line is available. Selection of a desired channel is achiered by a multiposition . switch provided as a part of the handset station. Both the page channel and the parti lias chenr.e?.s, which are independent, may be used simultaneously without interference. A page party line (with only one party line) handset station is installed in each elevator to permit communication in emergency situation. 4.1.2 INTRAPLANT TELEPHONE SYSTEM g An independent touchtone telephone system, the PBX telephone system, l is provided for uninterrupted private communication between the i following areas: the Control Room, Fuel Building, health / physics and i instrument shop areas, remote shutdown panel area, hot shop, Guard l House, reactor operating platform areas, intake structures, l Maintenance Building offices, Technical Support Center, Emergency l Operations Facility, Nuclear Operation Support Facility and 1 Administration Building offices and work areas. i s 4-2 () REVISION 3 MAY 21,1982 Ib p =-lh Dh , ' N' ' (Y"M *
, ' ' _ _ % _(N Y h ~ %h
- . . - -.- -. - - ._. -. -. . - - . . - ~. ~ . . . . . . . - . . _ .
CPSES/EP
) The PBX telephone system is integrated with the Intraplant Communication System through an isolating device to ensure that a single failure in either one of these two systems does not affect safe i and reliable operation of the other system. Power is supplied to the PBX telephone system from the non-ESF bus. When the PBX telephone system's normal AC power supply is lost, a number of predetermined telephone stations remain operable which derive their power from the public telephone system.
4.1.3 INTRAPLANT SOUND-POWERED TELEPHONE SYSTEM i This system consists of three subsystems per unit a, follows: Subsystem One: Maintenance Loops - Consists of s two channel !, hard-wired communication link between the control room area and critical plant areas. f Subsystem Two: Refueling Loops - Consists of a two-channel hard-wired communication link between the Control Room area, fuel handling area, and reactor operating floor. This subsystem is primarily provided for refueling operations. Subsystem Three: Emergency Loops - Consists of a two-channel, hard-wired communication link between the hot shutdown panel and safety-related equipment areas. The cables of this subsystem are routed in separate conduits from other subsystems. This ! l subsystem is primarily provided for communications l in the unlikely event the Control Room becomes inaccessible. The headset jack stations are conveniently located on panels in the Control Room and in critical areas. Communication can be established between the Control Room and any local panel or between two local panels by suitably plugging the headsets into jack stations which are mounted either in the panel or s nearby. This system provides standby communication capability and does not depend on external sources of power other than the human !. voice. ? - j - t 4-3 l ; O()
\ -
REVISION 3 MAY 21,1982 L (._, y . . ,_._ _ _7 , _ . _ . - . . _ . _ . , , , , ..y.._,
i i CPSES/EP l The number and location of sound powered telephone system receptacles are adequate to bring the plant to a hot' shutdown or a cold shutdown p from the Control Room or from the hot shutdown panel and other areas. t The sound powered telephone system can be used as a backup to the Intraplant Communication System in the critical equipment areas of the plant. One independent howler loop per unit is provided for sound-powered signaling purposes. 4.1.4 INTRAPLANT PORTABLE RADIO TRANSMITTER RECEIVER SYSTEM Two separate communication channels of unique wavelengths for the operating personnel, maintenance personnel, and fire fighting squad are provided to enable two-way radio communication between the Control Room and various plant buildings. The Control Room is equipped with the hand-held transmitter-receivers. Portable transmitter receivers operating on either one or both channels are provided for use by operations, maintenance, and fire fighting personnel for communication between various areas of the plant. To improve reception from various plant buildings, monitor receivers I or coaxial slotted cables, or both, are installed as required in these j buildings. The radio transmitter carrier frequencies are chosen to j preclude interference with the Reactor Building radio controlled crane 1 and carrier frequencies used by the Switchyard remote supervisory f carrier current equipment. i f 4.1.5 PUBLIC TELEPHONE SYSTEM 0 The public telephone system is interconnected to the Intraplant < Telephone System (PBX telephone system) by trunk lines. This permits access to the public telephone system from the Control Room, TSC, EOF, NOSF, health / physics and instrument shop areas, remote shutdown panel, Guard House, hot shop, Maintenance Building offices, Administration [ Building of fices and work areas, reactor operating platform area, and intake structures. 4.1.6 TWO-WAY RADIO TRANSMITTER-RECEIVER SYSTEM (PLANT-TO-OFFSITE) { The two-way radio transmitter-receiver system is provided for i emergency communication between plant and offsite public safety I agencies. The system description'is provided in the Security Plan. r - P C l 4-4 k 0 l 1 4 REVISION 3 I MAY 21,1982 i I s _ . . - _ - _ _ _ _ _ _ _ ____ __i
I 3 CPSES/EP ' !qq 4.1.7 DIRECT TELEPHONE LINE TO THE SYSTEM DISPATCRER
.e As an aid to power plant and transmission system operation, a direct leased telephone line and speaker circuit is available to the CPSES i operator in the Control Room. This direct line is independent of the i PBX system. The System Operations Center, which is manned at all l times, makes the direct line available for outside communication in l case of emergency.
! 4.1.8 EMERGENCY EVACUATION ALARM SYSTEM The evacuation alarm is generated by a solid state multifrequency audio oscillator capable of producing five distinctive tones which can be heard over all plant paging zones via the Intraplant Communication , System. One of the distinctive tones is designated for the evacuation ! alarm signal. l The evacuation alarm system, including the multifrequency audio oscillator, is powered by a source available upon loss of offsite
power and ESF bus and provides a unique alarm signal to ensure personnel evacuation in case of an emergency. The alarm is initiated l by the Control Room operator in the event of a plant site evacuation j emergency.
t I 4.2 EMERGENCY NOTIFICATION SYSTEM I The Emergency Notification System (ENS) is a direct and dedicated telephone from CPSES to the NRC Operations Center. CPSES initiates contact with the NRC office, which is manned continuously by NRC technical staff " Duty Officers", by merely lifting the receiver from j its cradle. This action causes a ring at the Operations Centor. At CPSES, ENS extensions are located in the Control Room, the Technical Support Center and the Emergency Operati-1s Facility. During emergencies, this line shall be used exclucively for transmitting unevaluated data for which the audience is limited. 4.3 HEALTH PHYSICS NETIORK The Health Physics Network (HPN) is a direct and dedicated telephone system, akin to a long distance intercom system. Extensions of this system appear at the Health Physics office, Emergency Operations Facility, resident inspector's office and the Technical Support i i i i 4-5 i
b 4
REVISION 3 MAY 21,1982 ym# - - - - - em-
i i
CPSES/EP
' I Center. In contrast to thr2 ENS, the Health Physics Network telephones are not used for immediate notification. The system is activated by p/ C { NRC in the beginning of an incident and will remain open throughout the incident, for the collection of radiological and environmental 1 informa tion. ( i I f 4.4 FACSIMILE COMMUNICATIONS ' i [ Facsimile Communications capability is provided via the PBX between j the TSC, EOF and the NRC. The facsimile transceivers utilize dial up i telephones and must be attended in order to transmit or receive. 1
. i i
I < l l l l' l l l l
+
i I ! ) . i l l ! 1 i I 1 4-6 1 4 t i h i b 1 i REVISION 3 MAY 21,1982
.n,_ . = . . . - _ . . ,, . .m-~n - - - - -_= =_ : .. _= -am --+
_ . ~ . . - _ _ _ , - _ _ _ _ _ . - - - - - CPSES/EP
,e -
(3/ Table 4.1 Emergency Communication Responsibilities l EMERGENCY CENTER RESPONSIBILITY / IMPLEMENTATION CPSES EOF Emergency Coordinator / f Communicator i CPSES TSC TSC Manager / Communicators CPSES CONTROL ROOM Shift Supervisor / Control Room Personnel HOOD COUNTY EOC Hood County Sheriff / Dispatcher SOMERVELL COUNTY EOC Somervell County Sheriff / Dispatcher TEXAS DPS, DISTRICT 6A Commande r/ Dispatcher CPSES RADIOLOGICAL MONITORING TEAMS Field Team Communicator HOOD GENERAL HOSPITAL Hospital Administrator / Hospital Operator NRC HEADQUARTERS Duty Officer NRC - REGION IV Duty Officer l k f$) f REVISION 3 MAY 21,1982
= = =-_===_= :- -- - - -- - v
f !
* ~
l ??.
.u' w l l
i 1
.' CPSES/EP FIGURE 4.1
COMMUNICATIONS INTERFACES "
COHHISSION NRC lia
RECIONAL ,
TECilNICAL -
- OFFICE I l
SUPPORT ,;,, i ;- CENTER
,, ,, , , , , , , l i , s BACKUP - /
S' ' ! Il l N R E RY
~--
CPSES
,i s N 7-------- MONITORING ,
OPERATIONAI. I BACKUP TEAMS
I :
SUPPORT - -
"_-_7_-- -
DEPAR'INENT 01- 1 CENTER 0 - -- -- PUBI.IC SA N l s FACILITY * * * * * *
. ~ ~ ~ ' - A I - I %.e I i' I i.
i
-3 s / - i l l1 f .- ..-]..-.... . . . . _.:
lL- - - - Il00D i [ COUNTY ROOM - ' l SilERIFF s I l (- - - -
! N l i! .
s\s l l '1 i I! i SYSTEM il SOMERVELL }
} DISPATCilER SECURITY ~ ' ~ ~ - - ~ ~ - - - - - - - - ~ - - - ~ ~ ~ - - ' -" - ""
SilERIFF I. 'd OFFSITE Telephone (normal) SUPPORT SER- Telephone (leased line) REVISION 3 VICES & OFF- - -- Sound Powered System UTY PERSON- MAY 21,1982 I - . - - - - Two-liay Ra d io 4 - - - -- Teletype
- . . - Emergency Notification System (also represents IIcalth Phy. sics Network) l
CPSES/EP
~ ,s_ 5.0 PUBLIC EDUCATION AND INFORMATION _
(E
)
In order to keep the public in the plume exposure EPZ adequately informed a program will be formulated which will insure proper dissemination of general station information and emergency action L information, which, coupled with media releases, should minimize rumors. t The program will be jointly developed among the local governments, the i Division of Emergency Management, Texas Department of Health and l Comanche Peak Steam Electric Station. An information package will be ! prepared and distributed annually to each residence within the designated plume exposure EPZ. Revisions will be distributed as nece ssa ry. An independent company provides a mailing list that includes all residents in the two counties. This list, updated annually, is used to distribute a periodic newsletter and the annual emergency information package. Public meetings may be held occasionally to answer questions the residents may have about CPSES and Emergency Preparedness. The initial distribution of information packages will be made prior to fuel loading. Public notices and pasphlets placed in the various parks and commercial buildings should l inform the transient population. Persons visiting the Squaw Creek Reservoir shall receive information concerning their responsibilities 1 and expected response should circumstances require that the Squaw 1 Creek Park and Reservoir area be evacuated. e i This information package = hall include, but is not limited to, educational information radiation, a contact phone number for additional information, a list of protective measures (including advice about what to do if these actions are recommended) and instructions to the handicapped if assistance is required. Prior to each annual exercise, a press briefing will be conducted by TUGC0 Public Information personnel to acquaint the news media with the purpose of the exercise, and to present information and answer questions regarding emergency preparedness activities at CPSES. In the event of an emergency at CPSES. the news media will be invited to press briefings conducted by the designated Company spokesperson at the Nuclear Operations Support Facility auditorium or other alternate facility. To the extent possible, the Public Information Coordinator will coordinate these press briefings with State and local public information personnel. 5-1 1
')
REVISION 3 MAY 21,1982 m= __=___-__ _- - - - - - - - - -
-~ .- ~ ~~- ~
6 ! CPSES/EP 4 i j 6.0 EMERGENCY FACILITIES AND EQUIPMENT
~
l i ) This section identifies, locates and describes the emergency I facilities and equipment utilized by the CPSES Emergency Organization. l The Control Room, because of its role in normal station operations is { always functional and thus not considered in this discussion.
Activation of a facility and the level of staffing is dependent upon
! the Emergency Action Level. Specific details concerning the
activation and staffing of each facility are delineated in the
? Procedure EPP-204 " Emergency Facility Activation". A facility is ' considered functional when at least half of its assigned station l personnel and the facility manager have arrived at the facility. These facilities are capable of continuous operations for a protracted period of time. ! 6.1 TECHNICAL SUPPORT CENTER
The Technical Support Center (TSC) is located in the observation area, i elevation 840'6" of the Control Building, above the Control Room. In y this location the TSC has the same radiological and ventilation i protection as the Control Room and the TSC personnel can observe the
] activity in the Control Room. The TSC is approximately 1500 sq. ft. in size. It contains interactive terminals to Lne Safety Parameter Display System (SPDS) and the Radiation Monitoring System (RMS), , as-built station drawings and flow diagrams, status boards, a i technical library and communications equipment.
~
The TSC staff consists of management and engineering personnel. The TSC Manager is supplemented by the TSC Advisor who is the liaison between the TSC and the OSC and by the Emergency Engineering team which is directed by the Engineering Team Coordinator. The TSC staff is augmented by five representatives from the NRC. The TSC staff, aided by the SPDS, RMS, Control Room supplied data and , the technical library, assesses the engineering aspects of the accident, evaluates possible solutions and assesses the current offsite and onsite radiological conditions. In addition, the TSC i staff relieves the Control Room staff of peripheral duties, such as communications with offsite authorities and administrative functions and decisions, thus allowing the Control Room staff to concentrate on reactor operations. For a Site Area Emergency or General Emergency; i.e., when the EOF is activated, the TSC shall continue assisting the 6-1
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] I l Control Room and assessing in-plant situations and transfer all q offsite related activities to the EOC. j i j 4 'l 6.2 OPERATIONS. SUPPORT CENTER i 1 The Operations Support Center (OSC) is located south of the Turbine l Building at elevation 810' and is approximately 1000 square feet in ! 1 size. Upon the declaration.of an Alert or higher class emergency, the j Emergency Repair and Damage Control Group and other station personnel y as needed shall assemble at the OSC unless otherwise directed by the
. Emergency Coordinator. }
h ! ji The OSC shall contain er.ergency kits, respiratory protection ! j equipment, auxiliary hghting, communications equipment and first aid 3 equipment to supply che emergency response teams and expedite their 4 e f fort s.
} 6.3 EMERGENCY OPERATIONS FACILITY e
j The Emergency Operations Facility (EOF), attached to the Nuclear -j Operations Support Facility (NOSF), is located 1.2 miles west of the j station in an optimuu meteorological sector. This location allows q convenient access to onsite arid of fsite areas. Decontamination a facilities, a control room simulator, nuclear operations training h personnel, laboratories and classrooms, a library, equipment for j processing personnel monitoring devices, interactive terminals for the
; SPDS and RMS, and the news media / visitors center within the NOSF are available to the CPSES Emergency Organization. If evacuation of this g facility is required, the Emergency Operations Center in either 4 Somervell County or Hood County shall be utilized as an alternate EOF.
1 !j The working space in the EOF, approximately 3200 square feet, should !j accommodate 35 persons, including 10 federal emergency response j personnel. Provisions for State and local personnel may be made available as necessary. Within the working space dose assessment, l communications and decision making activities are performed. Field j monitoring samples shall be isotopically analyzed at the EOF or a j similarly equipped facility and the data transmitted to the dose I assessment personnel. ! 4 i - i ) 1 - 1 1 1 j 6-2 I 4 Il
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h 9 t REVISION 3 l MAY 21, 1982 +.~ ~ .~. ,.
w.wm.w.w. ~ - - _ - - - ~ - - - -
_- - _ . -n. - l l CPSES/EP i d f The EOF shall be activated for a Site Arca Emergency or General j r~)s
b. Emergency. Once activated, the EOF personnel shall be responsible for g the following functions: recommending protective actions to the i
I public officials; maintaining communications and coordination of personnel exposures with offsite support and emergency response l organizations; assisting TSC and control room personnel in the [ evaluation of plant parameters and proposed corrective actions; and i management of the overall CPSES response. These activities are { t accomplished with the aid of the RMS and SPDS computer terminals. i I The decontamination facility is designed to accommodate personnel evacuating from the station who may be contaminated and personnel returning from the field or from planned reentries into the station environs. The facility contains a sink, three showers, two personnel survey areas, dressing area and an interim radioactive waste and
material storage room. Whter used for decontanination purpose shall i be retained in a storage tank for later sampling and processing, if I required. The solid waste shall be introduced into the station l radioactive waste system when it is appropriate to do so.
l 6.4 STATE AND LOCAL EMERGENCY OPERATIONS CENTERS - f ! The State of Texas Emergency Operations Center (EOC) serving CPSES is located in Waco, Texas, and is the Department of Public Safety (DPS) l District 6A Office. This office is staffed 24 hours per day with the commanding Highway Patrol Officer in charge of the Regional EOC. Any
notification of an emergency at CPSES should be transmitted to the Regional EOC by way of a dedicated telephone line from CPSES to the Regional EOC. The E0C in Waco shall notify the State EOC in Austin from where the State's emergency operations responae would then be activated. The " Texas Management Plan" is the operating document for the State.
The Emergency Operations Centers for the two county governments surrounding CPSES are the Hood County and Somervell County Sheriff's Offices. The Sheriff's of fices will normally be notified of an emergency at CPSES by the DPS; however, CPSES may contact them h directly. The Sheriff's office shall initiate the county " Emergency Operations Plan". A Texas Utilities representative, familiar with station systems and the CPSES Emergency Plan, shall be sent to the local EOC's, if required by the local EOC Manager. He functions as an f, 6-3 (~ f REVISION 3 MAY 21,1982
. _ _ . _ _ _ m ,. .y _._, _ . .
m
n _ _- -.- .- = - - _ _ _ _ _ _ _ :. , _ n s l . CPSES/EP i j advisor to the local E0C Manager and could act as a liaison between O j that Manager and CPSES. He is not a spokesperson for the Company. 2 y 6.5 EMERGENCY AID FACILITIES I I
First aid stations are located in the Turbine Building across from the j j Health Physics office and in the NOSF. These stations are equipped j s with standard first aid supplies and stretchers.
[ Decontamination stations are located in the turbine building and the 7 ? NOSF. These stations are equipped for personnel decontamination with $ showers, sinks, supplies and spare clothing. The NOSF decon facility {' . sinks, showers and floor drains normally drain to a non-radioactive
waste system; however, if need for radiological purposes, all' water
I generated in this area is diverted to a holdup tank for subsequent I processing.
6.6 EMERGENCY EQUIPMENT AND SUPPLIES
; Each Emergency Response facility (the Control Room TSC, EOF and OSC and the Hood General Hospital) is supplied with eraergency equipment and supplies commensurate to the response expected from that facility.
The inventory of supplies in Section 15.0, Appendix J is representative of that stored in the facilities. Complete equipment lists and the surveillance requirements are available in the Procedure EPP-310 " Surveillance of Emergency Supplies". This procedure dictates an inventory check of the supplies once each calendar quarter and after each use or periodic testing. Exchange or removal of items I shall be controlled such that the prescribed inventory levels are maintained. . The EOF emergency supplies consist of three field monitoring kits, protective clothing, respiratory protection equipment, portable radiation monitoring equipment and miscellaneous maintenance-type equipment. These supplies are available for use by the field i monitoring teams, personnel stationed at the EOF, and personnel who
! may require to reenter the site. The TSC and Control Room are also i
stocked with emergency supplies to ensure their preparedness in the f event of an emergency. A detailed check list of this equipment and instructions concerning periodic testing and inventory are addressed in EPP-310 " Surveillance of Emergency Supplies". The OSC is also equipped with the necessary emergency supplies and equipment for use l . I 6-4 l O REVISION 3 MAY 21,1982
, , ~ m e -. . n __ _,. ,an _. _ .- wx __ __ v .-
I I CPSES/EP These supplies are available for use by-
.in an emergency condition.
{)
~s the O'C personnel, reentry teams, adn ERDC personnel.
I Thyroid blocking drugs shall be kept in bulk at the EOF. On hand ( supplies will provide protection for at least 200 station employees i for 5 days. Smaller quantities shall be maintained in the ' field monitoring kits, the TSC and the OSC. The supplies maintained at the Hospital shall contain protective clothing, monitoring equipment, and contamination control supplies and selected procedures for use by the Hospital staff. l The following systems and equipment are used by the Emergency Organization to assess operating systems status, in plant and offsite radiological conditions and the overall safety status of the plant. 6.6.1 SAFETY PARAMETER DISPLAY SYSTEM The Safety Parameter Display System (SPDS) provides assistance to Control Room personnel in evaluating the safety status of the plant. ' The SPDS serves to concentrate a minimum set of plant parameters from which the plant safety status can be accessed. More detailed plant i information is provided by secondary displays. The SPDS information is based on sof tware and displays developed for the Safety Assessment System (SAS). The SAS provides a centralized, i [ flexible, computer-based data and display system to assist Control Room, TSC and EOF personnel in evaluating the safety status of the plant. This is accomplished by providing to these personnel a high ' level graphical display containing a minimum set of key plant ; parame ters. All graphical displays are presented to the Control Room personnel on a high resolution multi-color CRT. i l All data displayed by the SAE is validated by comparing redundant ' sensors, checking the value against reasonable limits, calculating ' rates of change and checking temperature versus pressure curves. , i These displays (data) are updated and validated on an essentially I real-time basis. The SPDS vid-a-vid SAS is displayed on a CRT located in the Control i Room. This CRT contains the high-level display from which the overall safety status of the pit.nt is assessed. A dedicated function button 1 ( 6-5 l l l l l
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l REVISION 3 i MAY 21,1982 ) i
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CPSES/EP panel allows the operator to select from several predetermined second level displays at any time. The SPDS displays are also available to
, TSC and EOF personnel.
1 The primary display consists of bar graphs of selected parameter values, digital status indicators for important safety system parameters and digital values. The parameters indicated by bar graphs and digital values include: RSC pressure, RCS temperature, i pressurizer level, steam generator levels and steam generator
! pressures. Status indicators are provided for containment environment and secondary system radiation. Reactor vessel level (if available),
l core exit temperature, amount of subcooling and containment radiation p are indicated by digital values. Each of the bar graphs indicate wide-range values. If a parameter's value is outside the normal range, the bar color will turn red. In addition, there is a message area which will be used to indicate that an appropriate secondary display provides further information in case an off-normal value is detected or an event is occurring. Secondary displays may be selected by the operator. Trend graph
! groups of selected parameters, showing the last thirty minutes of l
plant operation are available. These trend groupings were chosen to keep like parameters or related parameters on one display "page". ' The total SPDS is not Class 1E and does not meet the single-failure l criterion. The sensors and signal conditioners (such as j preamplifiers, isolation devices, etc.) are designed and qualified to meet Class 1E standards for those SPDS parameters that are also used
! by safety systems. Furthermore, sensors and signal conditioners for
{ those parameters of the SPDS identical to the parameters specified j within Reg. Guide 1.97 are designed and qualified to the criteria
; stated in Reg. Guide 1.97.
I j The SPDS used in the Control Room is designed to an operational unavailability goal of 0.01. The cold shutdown unavailability goal 8 for the SPDS during the cold shutdown and refueling modes for the l reactor is 0.2. The unavailability goal of 0.01 is more stringent j than can be reasonably achieved without some redundancy. Therefo re, i dual minicomputers, data multiplexors, and other critical peripherals will be installed. Power supply is from Non-1E Battery, Uninterrupted j Power Supply System. , e i le i 6-6 i i () REVISION 3 { MAY 21,1982
l 1 CPSES/EP 1
,s 6.6.2 EMERGENCY RESPONSE FACILITY COMPUTER SYSTEM ; Ic)
The Emergency Response Facility (ERF) computer system for CPSES consists of a system configuration as shown in Figure 6.1. The l overall system principally consists of:
a. Isolation devices with integral digiting equipment which will provide 12 bit resolution of the parameter ranges.

b. Fiber optic cable runs between the remote multiplexors/ isolators and ERF computer.
This system is considered to be the Data Acquisition System (DAS). The DAS will be powered by a non-1E, highly reliable power source. (UPS-battery system) Redundant minicomputers provide the data processing / distribution /and record keeping functions required. The minicomputers are located in the same room as the plant process computer, but do not rely on the process computer for any of its ERF System functions. The minicomputers are powered from a highly reliable non-1E battery /UPS system. The display system consists of color graphics display units implementing the Safety Assessment System Software. Two displays are located in the control room, three in the TSC, and two in the EOF. One of the control room displays is dedicated to the display of SPDS type parameters. The other displays have full display capability, including the SPDS type parameters, in addition to all other parameters available to the computer. The Control Room and TSC displays will be powered from non-1E, battery /UPS power supplies. The integrated ERF Computer System reliability design goal is to achieve 0.01 unavailability during all plant operating modes above
. cold shutdown.
6.6.3 RADIATION MONITORING SYSTEM l The Radiation Monitoring System includes the Area Radiation Monitoring l System (ARMS) and the Process Radiation Monitoring System (PRMS). A block diagram is shown on Figure 6.2. The basic ARMS (integrated with PRMS) comprises two dedicated u ? q 6-7 il l: 1 V u
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i ] REVISION 3 , MAY 21, 1982
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i microcomputers in communication with each other (one in each of two i central display co'nsoles), distributed dedicated microprocessors (one ( }) i for each local detector / monitor assembly), and a report computer. At each monitor, control, data processing, data storage, and multilevel [ alarming are performed locally by the dedicated microprocessor; also, processed data are communicated to central consoles. These monitor 2 functions are performed at each monitor independently of the rest of
; the system. This independence is insured by use of optical couplers in monitor input / output circuita and by the distances separating monitors. The Process Radiation Monitoring System provides a means j
for measuring and controlling radioactive process streams and
, e f fluents throughout the plant.
The RM-21 report computer is part of the PRMS. The function of the RM-21 report computer is to help nuclear plant operators meet the requirements of the U.S. Nuclear Regulatory Commission (NRC) governing 4 the assessment of routine and accident radiation doses. The RM-21 generates two basic calculations for atmospheric dispersion, (1)- i routine releases and (2) accident releases. For routine releases,
dispersion is calculated using the sector-average version of the

equations for atmospherie relative concentration (atmospheric dispersion factor) (X/Q). For accident releases, the sector-average and the centerline versions of the X/Q equations are used. These calculations are made in accordance with methodology in NRC Reg. Guide 3 1.111 for routine releases and, to some extent, in NRC Reg. Guide i 1.145 for accident releases (except that effluent plume meander is not
~; calculated for accident conditions). Each release point is considered separately so that the height of release and vent conditions are i accounted for. All calculations use the Gaussian plume model. ]
The RM-21 also generates dose calculations for routine and accident conditions using the computed hourly ef fluent radionuclide releases,
; dilution / deposition rates and site-specific data constants.
Dose calculations for accident conditions are for doses caused by exposure to the plume, that is, beta (skin), gamma (whole body), 1 thyroid (inhalation). Dose is computed by using the X/Q value and the
. Q (release) value, using the most recent data available. Results of 3 the dose calculations are printed for operator use or may be displayed j graphically as the gaseous release isopleth. Complete information on ' these systems is located in the FSAR sections 11.5 and 12.3.4.
6-8 ) () .i 'j REVISION 3 MAY 21, 1982 h; m . _ _- _ _- ___-_- -
CPSES/EP
l. 6.6.3.1 Area Radiation Monitoring System The Area Radiation Monitoring System ( ARMS) continually monitors radiation fields in various representative regions within the plant.
Table 6.1 lists the parameters for this system. 6.6.3.2 Process Radiation Monitoring System The Process Radiation Monitoring System (PRMS) provides a means for assessing radioactivity levels in plant process and effluent streams, l and controls plant process and effluent streams including the handling and processing of radioactive waste. Table 6.2 lists the parameters j for this system. 6.6.4 HEALTH PHYSICS INSTRUMENTATION The Radiation Protection Section maintains a supply of Health Physics laboratory and portable surveying equipment. While this equipment is used routinely for normal operations, it is also available to supplement the emergency radiological monitoring equipment. Tables 6.3 and 6.4 list this equipment. 6.6.5 METEOROLOGICAL MEASUREMENTS PROGRAM The meteorological measurements program of the Comanche Feak Steam Electric Station shall consist of the following:
1. A primary meteorological measurements systen.

2. A backup meteorological ecua: cments system.

3. A system for making var tan t- time predictions of the atmospheric ef fluent transport and d4fiusion.
l To accomplish these goals, the pre-operational meteorological l instrument system, Table 6.5, will be modified to transmit meteorological parameters to the Meteorological Instrument Panel in the Control Room and the Radiation Monitoring System computer. The parameters, which are wind speed and wind direction at 10 and 60 meter levels and delta-temperature between the 10 and 30 and 10 and 60 meter levels, will be 1) continuously recorded at the Meteorological 9 6-9 t 4 REVISION 3 MAY 21,1982
. . _ . _ _ . ~ . . _ . _ _ , - - . _ _ .,... y ._ ... _ . - ,. y _ ,
CPSES/EP Instrument Panel'and 2) scanned once per minute by the Radiation - Monitoring System computer where they will be averaged each hour and stored. A time-history of the meteorological data will be available in analog form (strip charts) and from the hourly averaged digital data provided by the computer. The anbient temperature at the 10-meter level will also be displayed on strip chart recorders on the Meteorological Instrument Panel in the Control Room. The computer will keep treck of current averages of diffusion meteorology, measured ef fluent release rates, and the inventory for fission products released. The system will include the required software which will permit plant operators to make real-time, site specific estimates and predictions of atmospheric effluent transport and diffusion during and immediately following an accidental airborne radioactivity release from the plant. A viable backup system to provide measurements representative of site conditions of wind speed and direction and delta-temperature for substitution of lost or in; slid primary data vill be available before fuel load of Unit One. The operational program will be con. ducted in accordance with the requirements specified in Regulatory Guides 1.21 and 4.1, proposed revision 1 to Regulatory Guide 1.23, and revision i to NUREG-0654. Further details of the program are described in the CPSES FSAR, Section 2.3. In the event of an emergency condition at CPSES, should additional meteorological data or forecasts be required, the National Whather Service office in Fort Worth would be contacted. 6-10 h REVISION 3 MAY 21, 1982 or . . :n v mi ..m m m m-= - - -
== 1
[ O CPSES/EP NJ TABLE 6.5 METEOROLOGICAL INSTRUMENTATION (Preoperation Phase) Measurement Level (meters) Instrument Wind Speti 10 & 60 6 cup Anemometer Wind Direction 10 & 60 Wind Vane Temperature 10, 30 & 60 Thermistor Composite Aspirated Shield (Temp., Dewpoint,
& AT) i Dewpoint 10 & 60 Lithium Chloride Dewcell ! Delta Temperature (AT) 10-30 and 10-60 Thermistor Composite Precipitation Surface Tipping Bucket Rain i' Gauge l
Total Solar Radiation 1 Pyranometer Net Solar Radiation 1 Net Radiometer Note: The meteorological equipment is being upgraded to comply with NUREG-0654 and Reg. Guide 1.23. This equipment modification shall be re flected in the plan when it becomes available. I I 6-11 1
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REVISION 3 MAY 21,1982
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i ^~ l 1 1 j 6.6.6 SEISMIC MONITORING
)
d Seismic monitoring is provided within the plant so that in case of an i earthquake, sufficient data is generated to permit verification of the j dynamic analysis of the plant and evaluation of the safety of
; continued operation.
1 The seimnic instrumentation comprises the following instruments: 1 1. A triaxial time history accelerograph, which consists of triaxial
;x acceleration sensars, a seismic trigger, a magnetic tape recorder i and controls, and a magnetic playback unit. The function of the j triaxial tLae history accelerograph is to measure and permanently i record absolute acceleration as a function of time during an
[! earthquake. 1, j 2. A triaxial peak accelerograph, which is designed to permanently record peak seismic accelerations of seismic Category I equipment and piping. 1
3. A passive response spectrum recorder, which is designed to
; perntnently record spectral accelerations corresponding to i; specified frequencies and located at the foundation of the 4 Containment Building and the supports of the seismic Category I equipment and piping. ,
j 4. A response spectrum switch, which is designed to provide a signal j for remote, immediate indication that any specified, preset,
; spectral acceleration has been exceeded.
1
; 5. A seismic switch, which is designed to provide a signal for i
renote Lnmediate indication that a specified, preset, l acceleration has been exceeded. i The seismographic instrumentation is fully described in section 3.7B.4
; of the FSAR. .i 6.6.6.1 Location and Description of Instrumentation i ) The seismic instruments , enumerated in the previous section are , situated at the following locations:
1 6 1 3 6-12 'l () 1 ] REVISION 3 MAY 21,1982 1
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1. The triaxial time history accelerograph has three triaxial I acceleration sensors. The first is located at the top of the I
Containment Building mat, the second is located on the exterior { face of the Containment Building wall at elevation , l 1000 ft. 6 in., and the third is located in the " free field". These sensors have the function of sensing the absolute seismic j accelerations in two horizontal orthogonal directions and in the vertical direction at the Containment foundation, on the i Containnent structure, and in the " free field". The data collected by the sensors are transmitted to the recorder. } In addition, s seismic trigger is installed on the Containment 3 Building foundation and is connected to all three sensors and the f recorder. The function of the seismic trigger is to start the a time history accelerograph whenever a preset threshold is exceeded for any of the three directions. A time delay device I keeps the entire system operating for five seconds after the last motion above the threshold of the trigger. The triaxial time history accelerograph also includes a magnetic tape recorder and a playback unit which records the signals for j accelerations versus time in the three orthogonal directions and provides inmediate visual display of the recorded time histories on a strip chart.
2. The triaxial peak accelerograph is a passive instrument that
$ requires no power source to sense motion and to record data. It 8 is used at one of the steam generators, on the reactor piping, [ and on one of the safety injection pumps in the Safeguards Building for recording the peak seisnic accelerations on the equipment and systems. 4 i 3. The passive response spectrum recorder is used on the Containment ; i Building foundation, on one of the steam generator compartment walls, and near one of the safety injection pumps in the Safeguards Building for recording seismic responses at these locations for different preset frequencies. i 4. The response spectrum switch is located on the Containment Building foundation and is used for transmitting to the Control Room a signal whenever the response in any of the three
orthogonal directions exceeds a preset value.
i e i i
! 6-13 1
1 REVISION 3 MAY 21, 1982 1 U_ Y [m *
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5. The seismic switch is located on the Containment Building foundation and is used for transmitting to the Control Room a signal whenever the acceleration in one of the three orthogonal directions exceeds a preset value.
A schematic diagram indicating the locations of all seismic instrumentation is presented on Figure 6.3. Based upon the information contained in Section 2.5 of both the CPSES FSAR and ER, which discuss the low probability of a significant seismic event occurring within the CPSES area, the requirement for accessing offsite seismic monitoring equipment is considered ( unnecessary. l 6.6.6.2 Control Room Notification ! In case of any seismic activity of sufficient intensity to activate the seismic instrumentation, the Control Room is alerted by means of I the seismic annunciation system, which consists of visual and audible i alarms. Approximately 15 seconds af ter the basement acceleration falls below the threshold level, the recorders are shut off. Operations personnel then obtain the strip chart records of the acceleration time history in the longitudinal, transverse, and vertical directions. These records are then compared with previously prepared templates, on which allowable acceleration amplitudes have been clearly marked, to determine whether continued plant operation is e considered safe or the plant should be shut down pending further evaluation. 4 The seismic trigger is set to activate the instrumentation at an [ acceleration level slightly above normal ambient vibrations and well below the postulated OBE " free field" ground acceleration. Any response of the seismic instrumentation above this predetermined L threshold is monitored by Operations personnel as previously [ described. In addition to this data, the operator obtains the response spectra to j aid him in taking appropriate action if an earthquake larger than the j OBE has occurred. These response spectra are generated by several
, response spectrum recorders installed at selected locations in or near i
seismic Category I structures, systems, and components, as described i in Section 6.6.6.1. 6-14 i l % l s) I I REVISION 3
! MAY 21, 1982 b
i 1 t .c m .x m = = = m m m w e1.<x : m w :- n =- -- -- -----
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) 6.6./ HYDROLOGICAL HONITORING i
The hydrological monitoring equipment used by CPSES provides data on l the water leve' ~ Squaw Creek Reservoir. The level indicator is not i capable of bei. read in the Control Room. To compensate, operators I periodically read the level indicator and relay the information to the ' Control Room. I Based upon the information contained in Section 2.4 of both the CPSES . FSAR and ER, which discuss the low probability of a sigt.ificant hydrological event occurring within the CPSES area, the requirement ' for accersing offsite hydrological monitoring equipment is considered unneces sary. l 6.6.8 PROCESS MONITOR INSTRUMENTATION l ! The SPDS system and ERF computers provide graphic displayed data to ; l the Control Room personnel and to the CPSES Emergency Organization ! j personnel in the TSC and EOF. This information is also available to f the operators by remote monitoring indicators located on the l operators' control board. The following three tables list the principal systems: l Table 6.6 Reactor Trip System Instrumentation ? - f Table 6.7 Control Board Indicators Table 6.8 Control Board Indicators' Parameters 6.6.9 FIRE DETECTION INSTRUMENTATION This section identifies and describes the Fire Detection l Instrumentation used at CPSES. This information is found on Figures i
6. 4. A complete description of the CPSES Fire Protection Program is located in the FSAR section 9.5.1.
I 6.6.9.1 Detection System Columns 19 and 20 on Figure 6.4, the Fire Hazards Analysis chart, list the fire detectors utilized. at CPSES. The following information ! explains these detectors. j i
. l l .
6-15 l i l REVISION 3 , 3 MAY 21,1982 I :: ;mz == .. ~ , u_ z P=.a,- JNFC N CTS T "l%S?ITZ*T C"~"S S-TL MC'Au" h ^N
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. CPSES/EP 1
l
1. Column 19 Fire Detection Systems - Type ()
i This column identifies the number and type of detectors located in each fire area, according to the component of combustion I (f .e. , heat or products of combustion). Detectors are selected' in accordance with the class of combustible material, the type of , equipment located in a fire area, the type of fixed fire ; i protection system installed in the area and the physical arrangement of the area. The types are as follows: <
a. Ionization detectors (ID) respond to products of combustion. >

b. Thermal detector (TD) responds to heat of combustion.

c. Infrared detector (IR) responds to the presence of flame. l t
The term "none" shall indicate that there are no detectors in the area. ;
2. Column 20 Fire Detection Systems - Intended Service l This column identifies the designated function of the Fire Detection System, subsequent to activation, in an individual fire area. The respones subsequent to actuation consist of: !

a. Local alarm (LA), which annunciates' an alarm in the specific ;
fire area.
b. Remote alarm (RA), which annunciates an alarm in the Control Room and throughout the plant.
3 I ) c. Fixed system actuation (FSA), which actuates the fixed fire : l protection system in the specific fire area. i
d. Water flow alarm (FA) which annunciates an alarm indicating i water flow to a fixed extinguishing system.
l l 6.6.10 POST ACCIDENT SAMPLING SYSTEM The CPSES Post Accident Sampling System (PASS) is supplied by the ! Reactor Plant Services division of Reactor Plant Services division of (
! General Dynamics in Groton, Connecticut. It is comprised of two {
r t 6-16 i j ! () ( REVISION 3 l MAY 21,1982
i -- t 1 t i ~ CPSES/EP l . t
~
(} independent units: Reactor Coolant PASS and Containment Air PASS. The reactor coolant PASS is capable of collecting a primary coolant or containment sump liquid sample as required by NUREG-0737. The reactor . coolant PASS is a dual module unit consisting of one sample module and j one remote operating module. The sample module is located in the Primary Plant Sample Room and contains the valves and components required to physically collect the sample. The remote operating module is located in the Switchgear Room (a low radiation area) and j contains the sample system mimic board, electrical controls, and l
; instrumentation readout necessary to operate the sample module ,
1 remotely. J] The Containment Air PASS has the capability of collecting a sample of i containment air as required by NUREG-0737. The Containment Air PASS j is a dual module unit consisting of one sample module and one remote operating module. The sample module is located in the Primary Plant i Sample Room and contains the valves and components required to physically isolate a sample of containment air. The. remote operating 1 module is located in the Switchgear Room (a low radiation area) and contains the sample system mimic board, slave valves, and nitrogen j flask required to operate the sample module remotely. j Operating procedures for the Reactor Coolant and Containment Post i Accident Sampling Systems will be developed prior to operation. n 1 6.6.11 0FFSITE RADIOLOGICAL MONITORING PROGRAM The Offsite Radiological Monitoring Program is addressed in the
Radiological Effluent Technical Specifications and conforms to the Branch Technical Positions requirements. .
; The Offsite Radiological Monitoring System include the following t p equipment: 9 airborne monitoring stations and 43 TLD's. The 9 j' airborne monitoring stations are designed for collecting particulate and radioiodine samples. The airborne monitoring stations are located i in and around the plant perimeter. The TLD's are designed for determining gamma dose and are located as follows: 16 TLD's are l
located on the plant perimeter (1 in each sector),16 TLD's are located between 4-5 miles from the plant (1 in each sector), and the remaining 11 TLD's are placed in selected areas. For exact locations ' and directions to the air sample station and TLD's refer to figure 6.1 j and procedure EPP-30,3, " Emergency Radiological Surveys." h 6-17 1 . {', h i REVISION 3 MAY 21,1982 9 i*r~~~ X ~:_~~?~~ % w - ~' ?; : z 2K':W R ' ...: w . # X v.~r?c u r 3 M w= 2 5 % vw w d -
t 0 \
?<
I CPSES/EP (s ' TABLE 6.1 (Sheet 1 of 6) - AREA RADIATION MONITORING SYSTEM PARAMETERS
t 1 Specified Instrtment Channel Nos. Detector Range -
Unit 1 Unit 2 Type Monitor Location (mR/hr) }
- Containment Building -
1RE 6290A ' 2RE 6290A Ionization Elevation 905 ft 9 in. 1.0E 03 to Chamber 1.0E 10 1RE 6290B 2RE 6290B Ionization Elevation 905 ft 9 in. 1.0E 03 to Chamber 1.0E 10 1RE 6250 2RE 6250 G-M tube Elevation 905 ft 9 in. 1.0E-01 to k 1.0E 04 y h 1RE 6251 2RE 6251 G-M tube Elevation 860 ft 0 in. 1.0E-01 to 1 j (critical- manipulator crane area 1.0E 04 s ity monitor) ' i j 1RE 6252 2RE 6252 G-M tube Elevation 860 ft 0 in. 1.0E-01 to 3 (criticality 1.0E 04 ) j monitor) [ i 1RE 6253 2RE 6253 G-M tube Elevation 860 ft 0 in. 1.0E-01 to ]N (criticality 1.0E 04 l monitor)
}
1RE 6255 2RE 6255 Ionization Elevation 808 ft 0 in. 1.0E 02 to f Chamber 1.0E 07 f L
I [ i, s ' REVISION 3 -
] MAY 21, 1982 ;
y __ . o -- z m -
=mr- mm _ - .m m x _m_. ___. m - . _ , . _ ,
h U . CPSES/EP TABLE 6.1 k (Sheet 2 of 6) d S I d AREA RADIATION MONITORING SYSTEM PARAMETERS f L Specified f* Instrunent Channel Nos. Detector Range i Unit 1 Unit 2 Type Monitor Location (mR/iir)
j 1RE 6256 2RE 6256 Ionization In-core instrumentation 1.0E 02 to l Chamber room Elevation 849 ft 0 in. 1.0E 07 l
1RE 6285 2RE 6285 Ionization Below in-core 1.0E 02 to ] Chamber instrmentation room, 1.0E 07 , l Elevation 831 ft 6 in. ! { Safeguards Building i k 1RE 6257 2RE 6257 G-M tube Personnel airlock 1.0E-01 to ! Elevation 831 ft 6 in. J 0E 04 i }! t l 1RE 6259A 2RE 6259A Ionization Mechanical Penet. area 1.0E+02 to f j Chamber Elevation 810 ft 6 in. 1.0E+07 , IRE 6260B 2RE 6250B Ionization RHR Pump room 1.0E02 to j i Chamber Elevation 773 ft 0 in. 1.0E07 j
, 1RE 6260A 2RE 6260A Ionization kHR Pump room 1.0E 02 to !
Chamber Elevation 773 ft 0 in. 1.0E 07 ! 1RE 6259B 2RE 6259B Ionization Mechanical Penet. area 1.0E02 to , Chamber Elevation 810 ft 6 in. 1.0E07 l 4 1RE 6286 2RE 6286 G-M tube Hot shutdown panel area 1.0E-01 to l f Elevation 831 ft 6 in. 1.0E 04 ',
\
IRE 6261 2RE 6261 G-M tube Sampling Room 1.0E-01 to l Elevation 810 ft 6 in. 1.0E 04 REVISION 3 MAY 21,1982 l
' c
i
n. >
O d, . .
CPSES/EP
'j TABLE 6.1 l (Sheet 3 of 6) j j AREA RADIATION MONITORING SYSTEM PARAMETERS !
i ! Specified l Instrunent i Channel Nos. Detector Range 1 Unit 1 Unit 2 Type Monitor Location (mR/hr) 1 l j 1RE 6291A 2RE 6291A Ionization Valve isolation tank room 1.0E02 to ,
! Chamber Elevation 790 ft 6 in. 1.0E07 l 1RE 6291B 2RE 6291B Ionization Valve isolation tank room 1.0E02 to j ChSmber Elevation 790 ft 6 in. 1.0E07 1RE 6292 2RE 6292 Ionization Electrical Penet. area 1.0E02 to i, Chamber Elevation 810 ft 6 in. 1.0E07 i i i l 1RE 6293 2RE 6293 Ionization Piping Penet. area 1.0E02 to Chamber Elevation 831 ft 6 in. 1.0E07 l o
IRE 6294 2RE 6294 Ionization Electrical Penet. area 1.0E02 to ! J Chamber Elevation 831 ft 6 in. 1.0E07 k - 1RE 6295 2RE 6295 Ionization Personnel airlock 1.0E02 to - Chamber Elevation 831 ft 6 in. 1.0E07 $ I
, 1RE 6296 2RE 6296 Ionization Electrical Penet, area 1.0E02 to j Chamber Elevation 852 ft 6 in. 1.0E07 9 p r j 1RE 6297 2RE 6297 Ionization Emergency airlock 1.0E02 to !
j Chamber Elevation.896 ft 6 in. 1.0E07 f: Auxiliary Building f i j XRE 6262 XRE 6263 Ionization Charging pump area 1.0E 02 to ! j Chamber Elevation 810 ft 6 in. 1.0E 07 i REVISION 3 , MAY 21,1982 ! i
_, - u ==. a., . - - - - - c==w== = = - ~ ~ -- ~ ~ ~*'="
~"'"=n I
J , 22 c, l C# U. i Ll CPSES/EP TABLE 6.1 i{ 0 f (Sheet 4 of 6) p {. , f: AREA RADIATION MONITORING SYSTEM PARAMETERS i ' Specified j Instrisnent Channel Nos. Detector Range Unit 1 ;
; Unit 2 Type Monitor Location (mR/hr) l >
l XRE 6264 XRE 6265 Ionization Filter - demineralizer 1.0E 02 to - Chamber area, Elevation 831 ft 1.0E 07 6 in. and 842 ft 0 in. ' i XRE 6266 XRE 6267 G-M tube Evaporator area j 1.0E-01 to i Elevation 810 6 in. 1.0E 04 ' t XRE 6268 XRE 6269 G-M tube Gas decay tank area 1.0E-01 to Elevation 852 ft 6 in. 1.0E 04 !
] and 862 ft 6 in. j XRE 6270 Ionization Recycle holdup tank 1.0E 02 to i t
Chamber area, Elevation 810 f t 1.0E 07 ) ' 6 in.
}
XRE 6271 G-M tube Hydrogen recombiner area, r 1.0E-01 to { 1 Elevation 810 ft 6 in. 1.0E 04 j XRE 6287 G-M tube Reverse osmosis < 1.0E-01 to l concentration tank area, 1.0E 04 {, Elevation 790 ft 6 in. (
XRE 6277 i G-M tube Filter drop area 1.0E-01 to j Elevation 810 ft 6 in. 1.0E 04 '
XRE 6288 G-M tube Fuel Building entrance 1.0E-01 to ' !q area, Elevation 860 ft 1.0E04 i 0 in. ' i REVISION 3 $ MAY 91.1987 0 [
i h CPSES/EP TABLE 6.1 0 (Sheet 5 of 6) AREA RADIATION MONITORING SYSTEM PARAMETERS , a Specified Instrtsnent i Channel Nos. Detector Range g ij Unit 1 Unit 2 Type Monitor Location (mR/hr) - q u
1RE 6298 2RE 6298 Ionization Ventilation Penet. area 1.0E02 to j Chamber Elevation 873 ft 6 in. 1.0E07
[e IRE 6299 '2RE 6299 Ionization Ventilation Penet. area 1.0E02 to r j: Chamber Elevation 886 ft 6 in. 1.0E07 " f : 1 Fuel Building .I g ) XRE 6272 XRE 6273 G-M tube Operating floor 1.0E-01 to ! i (critical- Elevation 860 ft 0 in. 1.0E 04 h
. ity monitor) "
b XRE 6274 XRE 6275 G-M tube Operating floor 1.0E-01 to P (critical- Elevation 860 ft 0 in. 1.0E 04 [ t ity monitor) L f 1 XRE 6278 G-M tube Genera'l area 1.0E-01 to Elevatilon 810 ft 6 in. 1.0E 04 g r XRE 6279 -M tube Vicinity of wet cask pit, 1.0E-01 to Elevation 838 ft 9 in. 1.0E 04 ['
+
XRE 6289 G-M tube Drtsn fill area, 1.0E-01 to ( Elevation 810 ft 6 in. 1.0E 04 t'; Turbine Building t
; XRE 6280 G-M tube Hot shop area 1.0E-01 to i Elevation 810 ft 6 in. 1.0E 04 I I,
O.
} REVISION 3 I:
6 MAY 21,1982 I: i
1. .
.s .e
[ (v W! . . !j CPSES/EP ! i TABLE 6.1 I j (Sheet 6 of 6) 3 l i
] AREA RADIATION MONITORING SYSTEM PARAMETERS l
Specified Instrisnent !
! Channel Nos. Detector Range ; '8 Unit 1 Unit 2 Type Monitor Location (mR/hr) 1RE 6284 2RE 6284 G-M tube Condensate polisher area, 1.0E-01 to Elevation 803 ft 0 in. 1.0J 04 l XRE 6283 G-M tube Hot lab area 1.0E-01 to j Elevation 810 ft 6 in. 1.0E 04 i: Electrical and Control Building l
f XRE 6281 XRE 6282 G-M tube Control room 1.0E-01 to i g Elevation 830 ft 0 in. 1.0E 04 l , i h i !l ! Il 4 y i 1 . o al] i: h
I L d L
[ REVISION 3 , MAY 21,1982 g
.aer - .w&m--=- _ _. - m aw a x3 - _ _ u.xww-e m. 4 , .u _ c . w. .2 , O,
( f*3 v : e 1 J, .l 8 CPSES/EP 'J 3 TABLE 6.2 > (Sheet I of 4) e PROCESS RADI ATIDs MONITORIN3 SYSTEM PARAKTERS d
.l Spec 1fied Detector Nos.** Monitor Locations Principa. ,1 Instrument 1 (E1., Column Coord., Isotopes Monitored Range j Unit 1 Unit 2 Detector Tyre Monitor Service Figure Numbers) Monitored Medium f
3 (uCf/ cal y Austilary Butiding XRE 5568A Beta Plant vent effluent El.873 feet 6 in. 1-131, 1-133 XRE 55688 Air SE-11 to SE-07 u . scinttilator - air Particulate (Fig. I.2-35, 1.5A-JA Cs-134, Cs-137*, a (off-line) and 8.5A-JA Co-58, Co-60 3, XRE 5575A Gasuna Plant vent ef flueet El.873 feet 6 In. 1-131*, XRE 55758 Air 4E+4 cpm /UCI 9
, sclettilator -- todine (off-Itne) (Fig. 1.2-35, 1.5A-JA I-133 and 8.54-JA) (
XRE 5570A Beta Plant vent effluent El.873 feet 6 in. Kr-85, Xe-135 XRF 55708 Air IE-06 to IE*05 h scintillator -- noble gases (Fig. 1.2-14; 85-ES and Xe-133* (off-Igne) Fig. 1.2-20, 95-ES) Flow diagram 9.4-9 i 4 XRE 5701 Beta Auxillary Butiding Vent duct, E1.873 f t. 6 in. Kr-85 $' I Air IE-04 to IE 00 scintillator ventilation air - (Fig.1.2-35, 2.5A-F A) Xe-13$*Xe-135 ( noble gases (in-Itne) Flow diagram Fig. 9.4 2 k 1RE 5637 2RE 5637 8 eta Main steam and Vent duct, E1.852 f t. 6 in. Kr-85, Xe-135 Air IE-04 to IE 00 h l-scinttilator feeduater area (Fig.1.2-13, 45-CS) Xe-133* d ventilation atr- and F1 . 1.2-19, 135-CS) noble gases (In-If ne) Flow d agram Fig. 9.4-4 0 XRE 5250 Wastegas(on-Igne) i 8 eta GWPS, El. 862 feet 6 in. Kr-85, Xe-135 Cas IE-01 to IE+04 scintillator (Fig. 1.2-34, 3A-GA) 5 Xe-133* 6 Flow diagram Fig.11.31 f ( IRE 4269 2RE 4269 Gamma Service water El. 190 feet 6 in. I-131, 1-133 1RE 4270 wter IE-05 to IE-01 p 2RE 4270 scintillator (off-line) (Fig. 1.2-31, 4A-GA) Cs-134, Cs-137, 3 { flow diagram Fig. 9.2-1 d ? 1RE 4509 2RE 4509 Ganna Component cooling El. 810 feet 6 in. 1-131 I-133 Wter th35 to IE-01 E H 1RE 4510 2RE 4510 scintillator water (cff-Itne) (Fig.1.2-32, 4A-FA to JA Cs-134. Cs-137, ! IRE 4511 2RE 4511 and 6A-FA to JA) Co-58, Co-60* g [ Flow diagram Fig. g.2-3 o XRE 5380 - Gasuna Boron recycle fluid El. 852 feet 6 in. 1-131, 1-133 Wter IE-05 to IE-01 j scintillator (In-line) (Fig.1.2-34,4A-KA) Cs-134. Cs-137, ( Flow diagram 9.3-11 f REVISION 3
- 21. 198, F
n E1 -
9 e et ,.3 y,, i b d* CPSES/EP a TABLE 6.2 }f (Sheet 2 of 4) PROCESS RADI ATION MONITORING SYSTEM PARAETERS i Specified 4 Detector Nos." Monttor Locations Principal Instrument i f' (El., Column Coord., Isotopes Monitored Range
? Unit 1 Unit 2 Detector Type Monitor Service Figure Mus6ers) Monit ored Medium (uCt/cmJ l4 XRE 5251 Gamma LWPS fluids El. 790 feet 6 in. 1-131, 1-133 jl XRE $252 scintillator Water IE-05 to IE-01 (in-line) (Fig. 1.2-31, 6A-HA, Cs-134,Cs-157, li XRE 5253 2.5A-HA, and 3A-F A) Co-58, Co-60* i l4 .
Flow diagrams Fig.s 11.2-4 jj and 11.2-5 XRE 4180 Gaauna Spent fuel pool El. 852 feet 6 in.
1 1-131, 1-133, Wter IE-05 to IE-01 I XRE 4181 scintillator dentneralizer sample (Fig.1.2-34, SA-KA and Cs-134. Cs-137, j (off-Igne) 6A-KA) Co-58, Co-60*
j Flow diagram Fig. 9.1-13
, i f XRE 3230 - Gamma Auxtllary steam E1. 790 feet 6 in. Co-60*, Co-58, ti hter l'E-05 to IE-01 l'
scintillator condensate (of f-if ne) (Fig.1.2-31, 3A-LA) Cs 134, Cs-137 Flow diagram Fig.10.4-16
t.
F 1RE 5698 2RE $698 8 eta Safeguards butiding- Vent duct, E1. 873 f t. 6 in. Xe-133*, Xe-135 Air IE-04 to IE-00 h scintillator ventilation air (Fig. l.2-35, 2A-HA Kr-85
'; (In-line) and 8A-HA) i l 0 flow diagram Fig. 9.4 2 l i: XRE 5700 - Beta Fuel Building Vent duct, E1.886 ft. i 4 Xe-133*, Xe-135 Air IE-04 to IE-00 scintillator ventilation air (Fig. l.2-35, 4A-KA) Kr-85 (In-line) Flow diagram Fig. 9.4-2 i l
) XRE 5702 -
Beta HVAC room ventilation Vent duct, E1.873 f t 6 in. Xe-133*, Xe-135 Air IE-04 to IE-00
g scinttilator air (in-Ifne) (Fig. 1.2-35, 4A-KA) Kr-85 1

, Flow diagram Fig. 9.4-2 I
, i f Safeguards Butiding I h IRE 4200 2RE 4200 Gamuna steam generator E1. 810 feet 6 in. h 1-131 hter IE-05 to IE-01 scintillator blowdown sample (Fig. I.2-11, 65-CS and Cs-134.1-133Cs-137 i (off-line) Fig. 1.2-17. IIS-CS) Co.58, Co-60* 6 Flow diagram Fig. 9.3-4 j sj 1RE 5179 2RE 5179 Gamma steam generator El. 810 feet 6 in. 1-131, 1-133, a hter IE-05 to IE-01 ( scintillator 81owfoun Prxessing (Fig.1.2-11,65-CS Cs-134, Cs-137, 4 el System fluid and Fig. 1.2-17,115-C5) Co-58, Co-60* 1 (of f-I f ne) Flow diagram Fig.10.4-10 r IRE 5502 2RE 5502 Beta containment air - El. 831 feet 6 in. Cs-137*, Rb-88, Air SE-11 to SE-07 scintillator particulate (Fig. 1.2-12, 65-OS I-133 E (off-line) and Fig. 1.2-18,115-05) $ Flow diagram Fig. 9.4-6 REVISION 3 MAY 21,1982 I ~ a !
...-.--_a -- .--- m _ -. -
1
-- , ? r.. ?
Y - ll f ll il CPSES/EP u j TABLE 6.2 (Sheet 3 of 4) 0 1 PROCESS RADIATION MONITORING SYSTEM PARAETERS 1 [ Detector Nos.** Spectited I Manitor Locations Principal ; Unit 1 (El., Column Coord., Isotopes Instroent . Unit 2 Detector Type Monitor Service Figure Numbers) Monitored Range Monitored Medium (uCt/cmj IPE $566 2RE 5566 Gaansa Containment air El. 831 feet 6 in. [ scintillator 1-131*, I-133 Air 4E+4 cpm /UCf todine (off-line) (Fig. 1.2-12, 6S-05 f4 j and Fig. 1.2-18,115-D5) 3 - Flow diagram Fig. 9.4-6 I
.t, IRE 5503 2RE 5503 p Beta j scintillator Containment air El. 831 feet 6 in. Xe-133*, Kr-85 Air a 3 noble gas (off-line) 65-DS Xe-135 IE-06 to IE-02 E (Fig.Fig.1.2 and 1.2-12'18, 115-DS) t . Flow diagram Fig. g.4-6 U 1RE 406 2RE 406 Geiger-Mueller Reactor coolant tube El. 831 feet 6 in. Co-60*, Co-58 Idater IE-00 to IE+05 I
letdown line Itquid (Fig. 1.2-12, 4.55-ES Cs-134, Cs-137 $ (off-line) and 1.218.12.55-ES) Flow diagram Fig. g.3-10 IRE 2325 2RE 2325 Geiger-Mueller Main steam noble gas tube El. 813 feet 6 in. Xe-133* Steam (on-line) (Fig.1.2 14, 65-ES Xe-135 , Kr-85 IE-01 to IE*03 - and Fig.1.2 20, Ils-ES) [. Flow diagram Fig. 10.3-1 % IRE 2326 2RE 2326 i L Geiger-Mueller Main steam noble gas El. 813 feet 6 in. Xe-133*, Kr-85 tube (on-line) (Fig. 1.2-14, 65-ES Steam 1E-01 to IE+03 Xe-135 and Fig.1.2-20, IIS-ES) k Flow diagram Fig.10.3-1 v IRE 2327 2RE 2321 Geiger-Mueller Main steam noble gas El. 873 feet 6 in. tube Xe-133*,Kr-85 Steam IE-01 to IE*03 h j (on-line) (Fig. 1.2 14,'65-ES Xe-135 3 q and Fig.1.2-20, llS-ES) ' Flow diagram Fig.10.31 I 1RE 2328 2RE 2328 Geiger-Mueller Main steam noble gas j [ tube El. 873 feet 6 in. Xe-133*, Kr-85 Steam i (on-line) (Fig. 1.2-14, 6S-ES Xe-135 IE-01 to IE+03 and Fig. I.2-20, its-ES) Flow diagram Fig. 10.3-1 Fuel Building XRE 4863 Gamma Spent fuel pool El. 810 feet 6 in. . XRE 4864 scintillator 1-131 Cs-137 Water IE-05 to IE-01 water (off-line) (Fig.1.2-38,SF-CF) Co-60*, Co-58 Flow diagram Fig. 9.1-13 i [ REVISION 3 MAY 21,1982 I s 3 f'. h I i p i
7 - - - _ ,. .e _ _- _~m =wma.ea m an wm:n- ~ = = : mw a < c ,. v.m ~u- r . : x- e w e :w l m. }j QM N("./ l h: l CPSES/EP l TABLE 6.2 i i (Sheet 4 of 4) ! i ! PROCESS RADI ATION MIAtlTORING SYSTEM PARAKTERS
4 i h
4 f Spec 1fIed l Detector Nos.** Monitor Locations Principal Instrument ' (El., Column Coord., Isotopes Monitored Range Unit 1 Unit 2 Detector Type Monitor Service Figure Numbers) Monitored Medium (utt/cm}3 Electrical and Control Building I* 1RE 5895 Beta Control Room El. 854 feet 4 in. Xe-133*, Xe-135 Air IE-06 to IE-02 i 1RE 5896 scintillator ventilation intake (Fig. 1.2-34, 2.9A-DA Kr-85 j
air (off-1tne) and 7.lA-DA) ,
ij Flow diagram 9.4 1 Turbine Butiding IRE 2959 2RE 2959 Beta Condenser off-gas El. 778 feet Kr-85 XE-133* Gas IE-05 to IE-01
t scintillator (off-line) (Fig. 1.2-22, 7T-FT Xe-135 'i 6 "
and Fig.1.2-27, 8T-FT) i Flow diagram Fig.10.4-3 . " [' 1RE 5100 2RE 5100 Gamma Turbine butiding El. 775 feet 3 in. Co-60*, Co-58, Water IE-05 to IE-01 f
], scinttilator drains 11guld (Fig.1.2-22, 4T4 T Cs-134. Cs-137 (off-Itne) and 1.2-27, Ilf-f T) I J Flow diagram Fig. 9.3-8 !;
F t i
?
.i l I ( s e
=
b REVISION 3 MAf 21,1982 a t t
E L.-_.__-___-_ -- _. _ .- - -- _ __ -- _ _ _ - -- - =
g j h '
) .
CPSES/EP
'; TABLE 6.3 !
l
; Health Physics Laboratory Equipment 4
Radiation
) Instrument Detected Detector Number Location Remarks l 1
l l Gama Spectroscopy System Gama Ge(Li) & NaI(TI) 1 Counting Lab Used primarily for I y effluents and
' environmental samples.
l Includes redundant MCA. !
)
Gas Proportional Alpha, Beta, Gama -- 2 Counting Lab Used for counting j Counter smears and radiochemistry !
~
samples. ; ll Liquid Beta -- 1 Counting Lab Used primarily for Scintillation tritium determinations. / TLD Reader System Beta, Gama -- 1 Health Physics Used for personnel. i. Neutrons Office dosimetry program.' l Includes redundant ! manual reader. Scalers Alpha, Beta, Gama Alpha probe, GM 2 Counting Lab or Used for counting high } Tube Hot Lab level smears or j
samples. ;
L Pocket Dosimeter -- -- 3 Health Physics Used for charging Charger Office pocket dosimeters. f 1 l REVISION 3 1 \ MAY 21,1982 4
\
- - - - - - . - - _ - _ _ _ - - ~ . . - - . - . -
J . 9 l; .. il CPSES/EP (,'] TABLE 6.4 I PORTABLE HEALTH PHYSICS EQUIPMENT. [ 3 Types of Instrument Radiations Range Monitoring a li GM Survey Meter Beta, Gama 0-500,000 CPM Contamination b 1 GM Survey Meter Beta, Gamma 0-2 R/HR Working Area 1 Radiation 1 I GM Survey Meter Beta, Gamma 0-1000 R/HR Working Area n Radiation
; Survey Meter Beta, Gamma 0-10,000 R/HR Working Area j
Radiation i 'i Survey Meter Beta, Gamma 0-200 R/HR Working Area i 1 Radiation f Neutron REM Neutron 0-5 REM /hr Working Area 5 Metar Radiation 1 F1 Neutron REM Neutron 0-50 REM /hr Working Area ji Meter Radiation Y Alpha 0-50,000 CPM Scintillation Contamination i Counter L ) Portal Monitor Beta, Gama Variable range Personnel switch Contamination Individual Beta, Gamma 0-999 mR Individual Personnel Exposure Monitor Pocket Gama 0-500 mR Individual h Dosimeter Exposure u -] Pock et Gama 0-5R Individual j Dosimeter - Exposure Pocket Gama 0-100R Individual Dosimeter Exposure 1 l r.'d
~-
REVISION 3 MAY 21, 1982 L , , ---- , _~m, -wm.--- . _- ~ .w.
. . _ , - - -. -- - - - - ~
---. _ - . . - - - -.-- . - - - - . -- . -- . . . . . .- .a c . . - . u-
_ -- _= _ __ _ CPSES/EP i 1 TABLE 6.5 l
.- i l
C) - l t l I I i l i i t l i 6 l l l - l I ! l, l i t REFER TO PAGE 6-11 f 1 k 1 l l t i i r I 6 9 l l REVISION 3 MAY 21, 1982 =====..r===:==-.=.,==,.,-..-
- m _. m .. . -m . . - .. - . ~_ _ _ _ ____ ,... - - _ . . _ _ _ _ _ CPSES/EP i
.m TABLE 6.6 l N
} REACTOR TRIP SYSTEM INSTRUMENTATION l Reactor Trip Signal Range i i 1. Power range high neutron 1 to 120% full power flux
2. Intermediate range high 8 decades of neutron flux neutron flux overlapping source range by 2 decades

3. Source range high neutron 6 decadeg of neutron flux flux (1 to 10 counts /sec)

4. Power range high positive +15% of full power neutron flux rate

5. Power range high negative -15% of full power i
neutron flux rate i l
6. Overtemperature N-16 N-16 0 to 15%gpower T 510 to 630 F l P ZR 1700 to 2500 psig F 4) -50 to +50 l
1, N-16 setpoint 0 to 150% 1 7. Overpower N-16 0 to 150% powgr } TC 510 to 630 F 3 N-16 setpoint 0 to 150% )
8. Pressurizer low pressure 1700 to 2500 psig

9. Pressurizer high pressure 1700 to 2500 psig

10. 9ressurizer high water Entire cylindrical portion level of pressurizer (distance between taps)

11. Low reactor coolant flow 0 to 120% of rated flow i 12. Reactor coolant pump 0 to 100% rated voltage .
j undervoltage i
13. Reactor coolant nump 50 to 65 Hz underfrequency i 14. Low-low steam generator M6 ft from nominal full 3 water level Toad water level g] 15. Turbine trip

a. Stop valve position N/A

b. Trip fluid pressure O to 500 psig I
g REVISION 3 g MAY 21, 1982
- _ ,-~..-. - . - ,. - _ ~ .- - - - --
-_w- _ - . . - - - - - --.. - . _ .. ~ ~. - - - - - = = = = ~ - =
I CPSES/EP p<d TABLE 6.7 (Sheet 1 of 9) J r h
CONTROL BOARD INDICATORS AND/0R RECORDERS
[ AVAILABLE TO THE OPERATOR (CONDITION II, III AND IV EVENTS) l
1. Wide range T h hot and T cold b
l a. The following minimun requirements are provided: g Two T hat and two cold indicator channels. The Thot channels are l on a separate power supply from the Tcold channels. The l capability of recording either T hat or T cold in one nonisolated loop is provided by recording each T hot and Tcold of each loop. h b. Range - 0 to 700 F.
! t
c. Purpose Il !
! 1) Maintain the plant !
l in a safe shutdown ' i condition < i l l
2) Ensure proper cooldown rate

3) Ensure proper a
relationship between i system pressure and temperat0re l 1 { t l. i : 1 REVISION 3 ,
- 21. 1,ez
_ _ = - _ - = _ _ - _ - - -
_ --. _ .u u.. ;.... - - - an+~ ~ ~ - - - i CPSES/EP dh 4 i t/ TABLE 6.7 (Sheet 2 of 9) j
2. Pressurizer water level l l

a. The following minimum requirements are provided:
Two channels on separate power supplies with one channel selected for recording. l
b. Range - entire distance between taps.

c. Purpose l d !
l \
1) Maintain coolant reactor coolant i inventory i i

2) Detemine return of water level to I pressurizer following steam break and steam generator tube I t
ruptures
i t

3. System wide range pressure !
l t
a. The following minimun requirements are provided:
Two channels 'on separate power supplies with one channel i recorded. 1
. i
b. Range - O to 3000 psi. !
i i i, h) ~ i, j REVISION 3 MAY 21, 1982 ! _ --,,,m__.__-~~... - ~ - - -
-' ~J
, _ _ _ _ _ _ - _ - - _ _ _ _ . . _ _ _ - _ _. . ~ . _ . .- _ ...
t I CPSES/EP i
, .o 1 1
kd TABLE 6.7 (Sheet 3 of 9) ) c. Purpose e i 1) Ensure proper ; i relationship between ! ! system pressure and temperature
\
{j 4. Containment pressure - narrow range b
a. The following minimtsn requirements are provided: '
Two channels on separate power supplies. Means are provided to 3 record one of the channels following a high energy line break ' inside Containment. f j b. Range - -5 to +60 psig
' l l r
c. Purpose t
r. i
1) Monitor Containment conditions following ~
primary or secondary i system break inside Containment I I
5. Steam line pressure j
)
a. The following minimum requirements are provided: !
Two channels per steam line on separate power supplies with one channel per steam line recorded. *
@" l f b. Range - O to 1300 psig.
t f s REVISION 3 MAY 21,1982 , hmw=:=~rwranrem . - ~ ~ ~~ n~ ~ - v ~ - ~ ~ ~ ~- ==-
I' l' i CPSES/EP i b- TABLE 6.7 (Sheet 4 of 9) I ! c. Purpose 5
1) Needed to determine
! type of accident that f has occurred and the ! proper recovery pro- ! cedure to use I i
2) Determine that plant is in a safe shutdown t condition i

6. Steam generator water level (narrow and wide range)

a. ihe following minimun requirements are provided:
Two channels (one narrow and one wide) per steam generator on separate power supplies with the wide range recorded.
b. Range - O to 100% of span for both wide and narrow range.

c. Purpose

1) Maintain adequate heat sink following an I

accident.
I
2) Needed in recovery l procedure following
, steam generator tube j ,. rupture : il) ; I I e REVISION 3 i MAY 21,1982 I h - - . - - _.u,,----m--~, _m _ - m ., .
-~~--- -]
1 l l CPSES/EP l l e c .. I
)
TABLE 6.7 (Sheet 5 of 9) l
3) Ensure that steam generator tubes are covered following a LOCA

7. Refueling water storage tank level 1
l l a. The following minimum requirements are provided: 1 l Two channels on separate power supplies. Means are provided to record one of the channels following a safety injection signal. Il
b. Range - O to 100% of span.
Time Needed
c. Purpose After Accident l 1) Detennine when to 12 hours I perform the necessary manual actions following i switchover from the injection phase to the l, recirculation phase of i safety injection after a LOCA
.s
8. Boric acid tank level (2 tanks)

a. The following minimum requirements are provided:
Two level channels per tank on separate power supplies. Means
, Q3 are provided to record one of the channels prior to Reactor Coolant System boration.
1 f l REVISION 3 l- m,_m . _ _m_ - ____,m_ < - - ..-- - MAY.21._1987_, _ . ._ ___
,i CPSES/EP l (S)
TABLE 6.7 (Sheet 6of9)
) ).
{ b. Range - O to 100% level. . l c. Purpose i I j 1) To ensure that borated l water is available for boration
9. Containment temperature

a. The following minimum requirements are provided:
Two channels on separate power supplies with each channel J recorded.
, b. Range - 0 to 3000F.
l
c. , Purpose q' 1) Monitor Containment conditions following primary or secondary 1 system break inside I
Containment j 10. Containment flood level 1
a. The following minimum requirements are provided:
Two channels on separate power supplies. {
b. Range - 0 to 9'-6" above floor elevation 808'-0".
js. } 3
REVISION 3 MAY 21,1982 E,
.A _ :'~.T 11"'J1 ~"T'"'b' A 'T iId b- ~-- - ~
- - _ _ . .==.__-_;. .. . _ - - - - - - - , _ a,w.
I CPSES/EP t y TABLE 6.7 (Sheet 7 of 9) I
c. Purpose

1) Indicate containment flood level during recirculation mode of l safety injection /
Containment spray following a LOCA
11. Containment hydrogen concentration

a. The following minimun requirements are provided:
Two channels on separate power supplies to be available within 12 hours follow'.ng a LOCA. Both channels are indicated and recorded locally. Control room indication only.
b. Range - O to 10% H 2 by volune.

c. Purpose

1) Monitor post-accident hydrogen concentrations inside Containment

12. Condensate storage tank level

a. The following minimum requirements are provided:
Two channels on separate power supplies, one channel is recorded. d)~ b. Range - O to 45 ft. REVISION 3 MAY 21,1982 w~,- n -- . .-. m _wn _- =_ :- __ ---= - -,--- - - -~
- - - - - . . = -
-. - - - u -- - ~
1 1 1
,1 CPSES/EP 1 , ,n ! fd TABLE G.7 (Sheet 8 of 9)
c. Purpose l
i 1 i
!! 1) Monitor Auxiliary l ; Feedwater supply y availability -
4 li 4 j 13. Containment Spray System monitoring i;'
a. The following minimun requirements are provided: ,
! For each Containment spray , ump, either pressure or flow is ]'l sufficient to monitor perfonnance of essential accident ) function. One channel each of low and pressure (per pump) is j indicated and recorded. Recording status at the onset of a j LOCA. Both diverse channels are derived from the same power-j supply as associated pumps. (Note: 4 x 50% pumps are provided.)
l:! i j b. Range i i
1) Pressure - O to 400 psig

2) Flow - 0 to 4000 gpm I
'; c. Purpose t 4 1
1) Monitor Containment Spray System for essential accident functions f
]
l-t
) REVISION 3 3
MAY 21, 1982 __.n_...,._.,--.:--.-----, - - - - - - - - - - - - - - -- - - = - -
CPSES/EP W, TABLE 6.7 (Sheet 9 of 9)
14. Containment pressure - wide range

a. The following are provided:
Two wide-range channels on separate power supplies. One of the channels is recorded. i
b. Range - 0 to 150 psig.
[ c. Purpose
1) To monitor containment pressure to three times design.

15. Radiation level inside containment

a. The following are provided:
Two mutually redundant, separated monitors for each unit, J designed and qualified to function in an accident environment. 7 i b. Range - 1 to 10 R/hr (60 kev to 3MeV photons) l
c. Purpose Monitor gross' containment
. radiation levels following a loss of coolant accident h
REVISION 3 l MAY 21,1982
%~ .w.- ..-_ _ -n,-,- --- -- . . . . .-
y .__ ___._ _ _ . . .-. ....._ _ m..~,.... ~ .m.m,_ . . - _ _ __ _ _ _ _ _ _ _ _ . _ _ - _. __ _ _ - _ . 1
/
(% k j
, CPSES/EP TABLE 6.8 (Sheet 1 of 10) 4
[ CONTROL ROOM INDICATORS AN0/0R Rett.1DERS AVAILA8tt TO THE OPERATOR TO l y MONITOR $1GNIFICANT PL ANT PARAETERS DURING NORM 4. OPERATION ! ) h No. of Channels Indicator / Parameter Available Range Recorder Location Notes f . Nuclear instrumentattoa
1. Source range
' t j a. Count rate 0 2 I to 10 counts /sec Both channels indicated; Control One 2-pen recorder is used to t either may be selected for board record any of the 8 nuclear i recording channels (2 source range.
2 intenmediate range and g 4 power range) $ I . 3 b. Startup rate 2 -0.5 to 5.0 decades / Soth channels indicated Control -
)
l sin. board 1
2. Intermediate range i a. Flux level 2 8 decades of neutron Both channels indicated; Control -
t i flux (corresponds to either may be selected for board 0 to full scale analog recording using the i I voltage) overlapping recorder in item I above the source range by 2 f ] decades j b. Startup rate 2 -0.5 to 5.0 decades / Both channels indicated Control - l min. board 'Y l REVISION 3 MAY 21.1982 y t I ( I $ a
o, - , - - - . _.~ - - - -~__ = m--------. :-- . . . . . .- -- _ - 1
< l
( CPSES/EP l 4 YABLE 6.8 f (Sheet 2 of 10) CONTROL ROOM INDICATORS AN0/0R RECORDERS AVAIL ABtf TO THE OPERATOR TO MONITOR SIGNIFICANT PL ANT PARAMETERS DURING NORMAL OPERATION No. of !. Channels Indicator / g Parameter Available Range Recorder location Notes 4 l f! 3. Power range , h !j a. thcalibrated ion 4 0 to 1201 of full All 8 groups of the ton NIS racks in - chamber current power current chamber current signals control room (average of the two top and average ., of the two botton [j uncompensated ton 'i ] chambers) ,
?
b
! b. Calibrated ton 4 0 to 120: of full All 8 groups of the ion Control -
l 4 chamber current power current chamber current signals board (average of the recorded (four2-pen [ two top and recorders) { average of the Recorder 1 - average of two bottom the upper two detector . uncompensated currents for 2 diagonally f fonchambers) opposed detectors j Recorder 2 - average of ) l the upper two detector k currents for remaining i .f detectors Recorder 3 - average of g the lower two detector currents for 2 diagonally e opposed detectors ... Recorder 4 - average of {; j the lower two detector currents for remaining detectors RtWISION 3 n.n 2i, ig82
)
4 g g , 4 r CPSES/EP f TABLE 6.8 P d (Sheet 3 of 10) I , r CONTROL ROOM INDICATORS AN0/OR RfCORDERS AVAILABLE TO THE OPERATOR 70 1 i j MONITOR SIGNIFICANT PLANT PARAMETERS DURING NORMAL OPERATION l No. of Channels Indicator / , Pa rameter Available Range Recorder location Notes 1 i c. Average of the 4 -60 to +605 Otagonally opposed Control -
's upper and channels may be selected board . ! average of the for recording at the l lower ton same time using recorder I i chamber current in item 1 difference
d. Average flux of 4 0 to 1205 of full All 4 channels indicated. Control -
l
; the average of povser Any 2 of the four channels board j l the top and may be recorded using I average of the recorder in item 1 J bottom ton chambers above. 'j .
e. Average flux of 4 0 to 1205 of full All 4 channels recorded Control -
the average of power board the top and average of the bottom ton
, chambers b
f
f. Flux difference 4 -30 to +305 All 4 channels indicated Control -
of the average board of the top and average of the bottom ton ,
I chambers J
REVISION 3 '. MAf 21.1982 ' I lj i I ( l
i e o , l CPSES/EP . , j TMLE 6.8 i (Sheet 4 of 10) I CONTROL ROOM INDICATOR $ AND/0R RECORefRS AVAILABLE TO TNE OPERATOR TO I MONITOR $!GNIFICANT PL ANT PARAMETER $ DURING N OPERATION No. of i l Channels Indicator /
, Parameter Available Range Recorder Location Notes 'h 9 Reactor Coolant Systee j ,
i
, 1. T average I/ loop 530' to 630% All channels inJ1cated Control -
{ (measureJ) board .5 i 2. N-16 Power 1/ loop 0 to 1501 of full All channels indicated; Control t (measured) power one channel is selected board f for recording I I a. Tcold or T hog 1.Th ot. O to 700*F Control All Thot channels are - l (measured, wide 1-Tcold recorded on one mittpoint board range) per loop recorder; all Tcold channels
] are recorded on another multipoint recorder
3. Overpower N-16 1/ loop 0 to 1501 of full All channels indicated; Control -
setpoint power w channel ts selected board { q for recording
) 4. Overtemperature I/ loop 0 to 150% of full All channels Indicated; Control - I N-16 setpoint power one channel is selected board for recording
5. Pressurtzer 4 1700 to 2500 psig All channels indicated Control - '
pressure board i
?
i v
REVISION 3 4 MAY 21,1962 h s
t 0 t q I i
.., y . ...._._-_.-._..y_.__,_,-.... . .,7..-_ . _ _ , . . . _ ..,_,..,..___7,, ,. ..,_, ,
I 1
q. ,.,
e t ) l
! CPSES/EP ; } TABLE 6.8 !
l (Sheet 5 of 10) + i CONTROL ROOM INDICATORS AND/OR RECORDERS AVAILABLE TO THE OPERATOR TO NOMITOR SIGNIFICANT PLANT PMAETERS DURING NORMAL OPERATION 1 j No. of l Channels Indicator / , Parameter Available Range Recorder Location Notes I I r 't i
6. Pressurtzer 3 Entire distance All channels indicated; Control Two pen recorders used, second t
, level between taps one channel is selected board pen records reference level f for recording signal l l 1 E
7. Primary coolant 3/ loop 0 to 1101 of rated All channels indicated Control -
f fIow fIow board t-
8. Reactor coolant 1/ loop 0 to 800 amps All channels indicated Control One chanret for each pimp; one
{ pump current board Indicator with a four position l, selector switch [ . g
}
9. Reactor coolant 1/ loop 55 to 65 Hz All channels indicated Cw.itrol One channel for each pump; one pump frequency board indicator with a four position selector switch

10. Systen pressure 2 0 to 3000 psig All chanr.els indicated and Control -
wide range recorded board Reactor Control System
1. Demanded rod speed 1 0 to 100% of rated The one channel is Control -
indicated board \. I h 2. Auctioneered 5300 to 6300F The one channel is Control 1 Any one of the Tavg channels Tavg recorded board into the auctioneer may be a bypassed I ' i REVISION 3 J d MAY 21.1982 l-F
n. 4 .C+ jO
$ Yd d l CPSES/EP j TABLE 6.8 f (Sheet 6of10)
CONTROL ROOM INDICATORS AND/0R RECORDERS AVAILABLE TO THE OPERATOR TO
- MONITOR SIGNIFICANT PL ANT PARAMETERS DURING NORME OPERATION f No. of l Channels Indicator /
Parameter Available Range Recorder Location Notes l 530' to 630 0F i i 3. Treference 1 The one channel is Control -
, recorded board 'l 4. Control rod If system not available, position borate and sample accordingly f ' i
a. Number of steps 1/ group 0 to 230 steps Each group is indicated Control The signals are used in ;
-l conjunction with the measured f of dananded rod during rod motion board withdrawal position signals (item 4c) to detect deviation of any individual rod from the demanded position; a deviation will actuate an alarm and annunciator
b. Full length rod 1 for 0 to 228 steps Each rod position is Control -
I measured each rod indicated board position i g 5. Control rod 4 0 to 230 steps All 4 control rod bank Control 1. One channel for each control bank demanded pos1t1ons are recorded board bank position along with the low-low 2. An alarm and annunctator is
limit alam for each bank actuated when the last control bank to be withdrawn reaches the withdrawal limit, when any rod control bank i reaches the low insertton

limit and when any rod control bank reaches the low-low 1nsertion 1toit .. REVISION 3 MAY 21,1982 } 4 5 't a i
_ _ .,aw.a - -
._- _ . n _ _ _ - _ ..,._n... -. - - . -.,. n ,- _ _
i
'q; ' .I , CPSES/EP i TABLE 6.8 (Sheet 7 of 10) .l CONTROL ROOM INDICATORS AND/OR RECORDERS AVAILABLE TO THE OPERATOR TO j MONITOR SIGNIFICANT PLANT PARAETERS DURING NORMAL OPERATION No. of i Channels Indicator /
lj Parameter Available Range Recorder tocatton Notes j
'l Containment System ,
f 6
1. Containment 4 -5 to +60 pstg All 4 channels indicated Control -
l pressure and one is recorded board
2. Costat ransrt 5 0 to 300"F All 5 channels indicated Control - Note b
$ temperature (
and recorded board k .. 3. Containment I per sep 0 to 36 inches Both channels indicated Control - Note b s ep level board - N I Feedwater and Steam systems 1 { [l p 1. Aux 11tary feedwater 1/ feed 0 to 300 gpm All channels indicated Control Two channels to measure the AFW flow Itne board flow to each steam generator. Note b
- 0
2. Auxtllary feedwater I per pump 0 to 25 pstg All channels indicated Control Note b F pop suction board pressure s
H
3. Aunt 11ary feedwater 1 per sump 0 to 200 psig All channels indicated Control Note b 1 pump discharge board pressure
{ t
4. Steam generator 3/ steam +7 to -5 f t from All channels indicated; Control -
g level (narrow generator nominal full load the channels used for board b range) level control are secorded REVISION 3 h l MAf 21,1982 j 1 i
1 (
i
a..~ c . -.-~.s.~ -..;...x.. ..-a
. . . : .xw . . ~ - , . .- .:-...~.... . .<- - , ~ . - . . . .
i j q . O
b' s
b l CPSES/EP TMLE 6.8 3
.} (Sheet 8 of 10) +
CONTROL ROOM INDICATORS AND/OR RECORDERS AVAll ABLE TO TE OPERATOR TO i MONITOR $lGNIFICANT PL ANT PARAETERS OURIE NORMAL OPERATION i
! i j No. of {
f Channels Indicator / I Parameter Available Range Recorder l ocation Notes 1
5. Steam generator ' 1/ steam +7 to -41 f t from All channels recorded Control - l t level (wide range) generator nominal full load board )
level
6. Programmed steam 1/ steam +7 to -5 ft All channels indicated v
,h generator level generator i signal r f
7. Main feedwater 2/ steam 0 to 120% of maximum All channels indicated; Control -
f p flow generator calculated flow ttie channels used for board ) f control are recorded i 1
8. m gnitude of signal 1/ main 0 to 1001 of valve All channels indicated Control 1. One channel for each main and controlling main 1/ bypass opening board bypass feedwater control and bypass feedwater valve ,
control valves 2. OPEN/ SHUT indication is [ provided in the control room for each main and bypass ( j feedwater control valve E4
] 9. Steam flow 2/ steam 0 to 1201 maximus All channels indicated; Control Accuracy is equipment capability;
]; generator calculated flow the channels used for board however, absolute accuracy a control are recorded depends on appitcant calibration f against feedwater flow [ t
10. Steam Itne 3/ loop D to 1300 psig All channels indicated Control - !
pressure and one is recorded board i ; J REVISION 3 r d MAY 21.1982 ( 4 b i 8 1 5 e
.i
f b
n :
J i U t
! h 1 0 J CPSES/EP i ^
TABLE 6.8 [ (Sheet 9 of 10) [
?
i i I CONTROL ROOM IN0lCATORS AND/0P RECORDERS AVAILABLE TO THE OPERATOR TO MONITOR SIGNIFICANT PL ANT PARAfETER$ DURING F.URMAL OPERATION f j No. of f
, Channels Indicator / {
Parameter Available Range Recorder Location Notes
11. Steam dump 1 0 to 100% of steam The one channel is Control DPEN/ SHUT indication is provided f
modulate signal dump valves open indicated board in the control room for each f j steam dump valve f (
12. Turbine impulse 2 0 to 1201 of maximun Both channel indicated Control OPEN/ SHUT indication is provided
[ t chamber pressure calculated turbine board in the control room for each ^ load turbine stop valve Engineered Safety Features Supporting Systems f 1. Component Cooling 1/ heat 0 to 200 pstg Indicator Control Note b
)
4 Waster System exchanger board i 5 pressure
2. Component Cooling 1/ heat 0 to 20,000 gpm Indicator Control Note b e Water System flow exchanger board [
i l
3. Component Cooling 2 0 to 1001 Indicated and Control Used for Component Cooling Water Water System recorded board Systen leak k surge tank level Note b f 4
[
) 4. Station Service 1/ pump 0 to 100 psig Indicator Control Note b [
Water System board f Pressure f f
5. Station Service 1/ pump 0 to 20,000 gpm Indicator Control Note b Water System flow board f
REVISION 3 4 l' MAY 21,1982 i 1 0 b a t t A
. . . , . . . . . . _ . . . . . . . . _ ~ _ _ . _ _ - . ! - - - g ., .I 1 s - QJ .
l l j CPSES/EP 3 TABLE 6.8 l (Sheet 10 of 10) CONTROL ROOM INDICATORS AND/OR RECORDERS AVAILABLE TO THE OPERATOR TO M)MITOR SIGNIFICANT PL ANT PARAETERS DURING NORWE OPERATION No. of Channels Indicator / f Parameter Available Range Recorder location Notes t . t . ' l 6. Control Room intake 2 10-6 to 10-2 41/cc Indicator / recorder Control room used for control room intake f duct radiation common area isolation 1 level l i
1. Control room to 2 0 to 0.5 in. H 2O Indicator Control roon Note b
'j atmospheric common area pressure diff. ? a Includes channel accuracy and environmental effects. b 'l i These monitors are part of ESF antog display. The operability of these monitors includes both normal and postulated accident conditions. 'l See Section 7.5.5.2 of the FSK. ) x d t I I s REVISION 3 { MAY 21. 1982 ? F I
y i ,
~' k..' .
INTEGRATED ERF COMPUTER SYSTEM 4 SENSOR SIGNALS FROM ONSITE > l . 11ETEOR0 LOGICAL NON SAFETY SAFETY SYSTEM
! DATA 1 SYSTEM SIGNALS SIGNALS
{ ,
! : SAFETY GRADE ; ISOLATORS i
1 l ' y v v .v
]
a , CONTROL R00ft , y y y q y SPDS '-
' ERF DATA '
i RADIATION HONITORING i SYSTEM SECOND RADIATION l' t
) DISPLAY HONITOR- i '
j
)
d ' i
't i l' i
s TECHNICAL SUPPORT CENTER y
] E0F RFVISION 3 I*
M. ' 21, 1982 g DISPLAY
> DISPLAY FUNCTIONAL FUNCTIONAL A AK M.R i
DISPLAY DISPLAYS ; DISPLAYS EMERGENCY PLAN i RADIATION RADIATION UNITS I and 2 DISPLAY
f10N! TOR > UI ^
f10NITOR
" INTEGRATED ERF i h _.
COMPUTER SYSTEM i FKkJRE 6.1 l h 5 1
_ _. ._. .-.__._m____ -_ . . . - m . ___:_ _- . _ . . . . .. .. m._-.m__. -
. . . - , - -....__._m_.. . _ _ . ..
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, ; ,LOOPl LEGEND ,j T (TYP) } g { (TYR) D : DETECTOR
I METECROLOGICAL 2 ,
TOWER o= OPTICAL ISOLATOR I 4 : c > a 33 : ANALOG TO DIGITAL l n o E8 CONVERTER . 2 2 {: PHYSICAL BARRIER 3 3 4 TRAIN A ! : TRAIN B
'GROUPI j '
SEISMIC ; GROUP 1 CAII , j
]
j Q nDI L N PROC. GRO"UP 1g PARTICllL ATE / LODINE / GAS
, _o_i to_, _ o o o INSIDE CONT _ROL ROOM PARTICULATE / LODINE / GAS, l
GRO P 1_r-@ q0J VENT MONITOR I VENT MONITOR 2 # PROC. L o (TYP) (TYP)
~
l l o CONTAINMENT AIR A CONTAINMENT AIR ~
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MONITOR ONIT 2)
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4, CONTROL "
ROOM - VENT ' i
]: , 'AAJIMU.34_pp., C.HA_NJE_LS_QR l MICROPROCESSORS mm3 h 4 MAY 21,1982 j $ i S "
i COMANCHE PE AK S E S U EMERGENCY PLAN UNITS 1 asus 2 f
' )
BIDCK DIACRAM r r)lCITAL RADIATION ,
, MrJNITOlt!NG SYSTEM _ __ _
frasE 6.2
;I j i i
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s 4 i - i PLAYBACK UNIT
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i CONTROL PANEL 1
. y = RoL 1 = : A = ANN -
i CONTAINMENT VESSEL WALL 1 E
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STRUCTURES OUTSIDE
.CONTAlHMENT ,(_ FREE FIELD ~~ '
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! TRIGGER ~ =
4 T/A SEISMIC IWSTRUMENTAT10M-l 1 0 . RACK (CONTROL ROOMT 4 SENSOR
=
T/A SS CONTAINMENTd VESSEL FOUNDATION LEGEND
; 3A / ' TIME HISTORY ACCELEROGRAPH REVISION 3 i .
MAY 21, 1982
; P/A PEAKRECORDING ACCELER04RAPH
COMANCHE PEAK S.E.S.
OR/s/
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RESPONSE SPECTRUM RECORDER EMERGENCY PLAN RESPONSE SPECTRUM SWITCH UNITS 1 and 2 SEISMIC INSTRUMENTATION J SE1 SMIC . SWITCH. SCHEMATIC DIAGRAM FIGURE 6.3
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\ < MAY 21,1982 T L.D. AND AIR i
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CPSES/EP h 7.0 ACCIDENT ASSESSMENT Assessment of the accident is accomplished using the Radiation Monitoring System and the Process Monitoring System which are described in Section 6.6. Also, discussed in Section 6 is the Post Accident Sampling System, the Area Radiation Mcnitoring System and the Radiation Process Monitoring System. The Radiation Monitoring System is capable of evaluating current Radiological data or accepting manually input (sta and projecting the dose isopleths. Procedure EPP-201, " Assessrant of Emergency Action Levels and Plan Activation", provides detailed examples and specific parameters to aid the Emergency Coordintor in accurately accessing and declaring an Emergency Action Level. Quick, accurate assessment of the emergency ensures that the proper emergency resources and actions are employed. The following is a general discussion of the monitoring programs for onsite and offsite assessment of radiological conditions. 7.1 CONTROL ROOM ASSESSMENT OF RADIOLOGICAL CONDITIONS The Radiation Monitoring System (RMS) receives data from several plant systems. The projections made by the RMS gives the Emergency Coordinator the necessary information to determine the consequences to the environment and the public and recommend protective actions to offsite officials. The Emergency Coordinator can utilize the Procedure EPP-301, " Control Room Accessment of Radiological Conditions", if the RMS System fails or for any other reason. This ( procedure utilizes the radiation monitor remote displays in the control room to provide radiological data to the Emergency Coordinator. With this data, the Emergency Coordinator should be able to evaluate the of f-site consequences with some degree of accuracy. 7.2 MANUAL ASSESSMENT OF RADIOLOGICAL CONDITIONS Should the RMS fail or the instruments that supply data fail or the reading go off scale, a prediction of the offsite consequences is made using worst case radiological data to ensure the safety of the public. If data is available and the RMS is not functional, each emergency response facility is equipped with a programmable battery powered calculator. This allows Radiation Protection personnel to continue an accurate assessment of the radiological conditions. The Procedure, EPP-302, "Of f-Site Dose Calculations", contains the necessary 7-1 i REVISION 3 MAY 21,1982 _ _ _ _ _ . _ ]
, CPSES/EP equations, instructions and basic forms to support a totally manual effort of calculating the offsite consequences. Also, if the RMS is inoperable, two Dose Assessment Kits are available. Each contains a ten (10) mile base map and seven (7) plume projection overlay, to visually illustrate the plume path and the affected sectors.
Data is also available from the field. CPSES field teams are equipped with a variety of survey equipment which includes a battery powered multi-channel analyzer. This equipment allows for field evaluation of air samples and should detect radioiodine concentrations as low as 1 x 10E-7 uCi/cc (micro-Curies per cubic centimeter).
7. 3 ONSITE AND OFFSITE RADIOLOGICAL CONDITIONS __ .
Normally, a release to the environment is monitored by permanently ; installed, real thne monitoring instruments located at the effluent I release points. These instruments are checked as necessary to estimate the release reate and/or magnitude of the release. In those , cases where the unavailability of monitoring instruments does not make { the above possible, (due to monitors being of f-scale or inoperable) design basis accident values or onsite monitoring team data shall be used. This information is provided for in Procedure EPP-301 " Control Room Assessment of Radiological Conditions". In the event of a release, protection of onsite personnel shall be given high priority. Onsite monitoring is conducted with the following objectives:
1. To determine whether external dose rates warrant evacuation.

2. To determine whether iodine sampling is necessary.
In the early stages of assessment, it may not be necessary to collect air samples if it has been determined that radioiodine is not a problem. Since noble gases always accompany iodine in a release, and in general will be released in substantially greater quantities, it is possible to set an upper limit on possible airborne iodine based upon a measurement of the external gamma dose rate. In general, air samples shall be collected if the general area gamma dose rate increases and/or inplant iodine monitor readings increase or alarm. 7-2 O REVISION 3 MAY 21,1982
CPSES/EP 7.3.1 ONSITE RADIOLOGICAL ASSESSMENT p& During an Unusual Event, the on-shift Radiation Protection technician performs the necessary onsite radiological assessment and sampling activities as directed by the Shift Supervisor. In the event that the emergency condition escalates to an Alert, the responsibilities for onsite radiological assssment are assumed by the TSC Health Physicist. As CPSES Emergency Organization personnel become available, onsite radiological survey teams are formed as required and dispatched by the TSC Health Physicist. Onsite radiological survey teams consist of at least two members; one shall be a Radiation-Protection technician. The onsite radiological assessment team or teams shall perform the required surveys in accordance with Procedure EPP-303 " Emergency Radiological Surveys". In the event that the emergency condition escalates to a Site Area or General Emergency, the responsibility for onsite radiological assessment is assumed by the Radiation Protection Coordinator. Communications between the Control Room, TSC, OSC, EOF and the onsite radiological assessment teams will be conducted in accordance with Section 4.0 of this plan. Transportation will be available to facilitate obtaining onsite radiological data. Based on the availability of a vehicle and the
( arrival time of CPSES Emeraency Organization personnel, onsite radiological survey teams should be deployed within 15 to 30 minutes af ter arrival onsite. Deployment tLne may vary due to the following i factors: the duration of the onsite briefing session; the time required to obtain and don protective equipment; and the time required to obtain and check the equipment specified in Appendix J of this plan.
l 7.3.2 0FFSITE RADIOLOGICAL ASSESSMENT In the event that a Site Area or General Emergency is declared, the Offsite Radiological Coordinator assumes the responsibilities for coordinating offsite radiological monitoring activities. The offsite radiological monitoring teams consists of at least two members; one shall be a Radiation Protection technician. 7-3 l REVISION 3 MAY 21,1982 ___ . _ . . - ---m -, _m
A CPSES/EP The Radiation Protection Coordinator shall dispatch the offsite radiological assessment team to the effected downwind sectors. This team shall perform external dose measurements, obtain air samples, determine contamination levels, and obtain vegetation and liquid samples, as required. This monitoring shall continue, as required, throughout the duration of the accident so that the need for protection measures can be quickly assessed. It is important that the locations at which environmental measurements are made be clearly , identified. Offsite environmental survey locations are identified in Procedure EPP-303 " Emergency Radiological Surveys". Communications between the TSC, EOF, and the offsite radiological assessment teams will be conducted in accordance with Section 4.0 of this plan. Transportation will be available to facilitate obtaining offsite radiologial data. Based on the availability of vehicles and the arrival time of CPSES Emergency Organization personnel, Offsite Radiological Assessmant Teams should be deployed within 15 to 45 minutes after arrival onsite. Deployment time may vary due to the , following factors: the duration of the onsite briefing session; the tLne required to obtain and don protective equipment; and the tLae required to obtain and check the equipment specified in Appendix J of this plan. 7-4
. (])
I l REVISION 3 l MAY 21,1982 l 4 . __ r-e w r- r c-- - m- we c - -=~wwve w we -
. CPSES/EP 8.0 PROTECTIVE RESPONSE Protective actions are ultimate measures taken when an uncontrolled release of radioactive materials has occurred. All unescorted personnel at the Station shall be given appropriate orientation to ensure that they are aware of how to respond in the event of an eme rgency. All escorted personnel are directed by their escorts in an emergency. Occupants in the EPZ are sent information concerning how they are to be notified and what they are expected to do in the event of an emergency. The nature of protective actions to be implemented, the criteria for their application, and the area involved or groups of persons for whom the protective actions would be taken are given below.
8.1 ONSITE PROTECTIVE ACTIONS 8.1.1 EVACUATION l In the event of an emergency, evacuation of specific onsite area or the site may be necessary to protect the people working at CPSES. An evacuation serves to reduce personnel exposure to the hazard, to warn other personnel to avoid the hazard and to aid in accountina for pe rsonnel. An evacuation, when ordered by the Emergency Coordinator, shall be initiated by an announcement over the station page system. The announcement should indicate the nature of the emergency, its location or the area to be evacuated and avoided, and the assembly area best suited for the incident. A site evacuation, or a Fuel Handling Building or Containment evacuation announcement should be succeeded by an audible alarm. Section 4 contains a description of this alarm. CPSES personnel not assigned to the energency response, visitors and construction personnel shall remain at the assembly area until either the emergency is terminated or they are released. Visitors shall remain with their escort or another CPSES individual for security and sa fety. Emergency response personnel shall gather at their designated assembly area unless directed to another location by the Emergency Coordinator. The assenbly areas include the hallway outside the Containment personnel hatch, the restricted area access point for the restricted area, the Administration Building parking lot for administrative 8-1 REVISION 3 M A'Y 21, 1982 . _ _ . . . ._ . _ . . - - - - _ - , _ ~-- - -s . - _ _ _
CPSES/EP personnel and those individuals inside the Protected Area and outside the restricted area, and the EOF for a site evacuation. The evacuation procedure, EPP-210, details the actions that shall be taken if an evacuation is required. Evacuation routes for the 10-mile EPZ are illustrated on a map in Section 15, Appendix N. A site evacuation affects the exclusion area around CPSES as well as the Station. Personnel in the emergency facilities shall remain in these facilities unless the situation or a complication warrants their evacuation. Squaw Creek Park and reservoir are also affected by a site evacuation. Squaw Creek Park, Inc. (SCPI) operates the park and is responsible for access to the reservoir during the parks hours of operation. SCPI is also responsible for the accountability and evacuation of the people in the park and on the reservoir. SCPI shall initiate their evacuation procedure when they are notified of a Site Area Emergency. As required, individuals evacuated under emergency conditions shall be directed to a location designated by the Emergency Coordinator for radiological evaluation. Security is ultimately responsible for controlling access to the exclusion area and may, with assistance from the county sheriff, aid SCPI in the evacuation effort. 8.1.2 PERSONNEL EVACUATED FROM THE SITE Personnel evacuated from the site shall assemble as prescribed in Procedure EPP-210, " Evacuation". At this point, Procedure EPP-307,
" Radiological Monitoring of Site Evacuees" is utilized. Control points will be established and personnel found contaminated shall be routed to the NOSF to be decontaninated.
8.1.3 INDIVIDUAL PROTECTIVE ACTIONS Personnel arriving or remaining onsite shall be afforded sufficient protective clothing to insure their ability to perform emergency response operations as needed. Respiratory protection is available as necessary and consists of full-face respirators with filters or self-contained breathing apparatus (SCBA). As a minimum, the Control Room is supplied with 6 SCBA's and 30 hours of reserve air supplies. The TSC, EOF and OSC are also supplied with SCBA's. Spare bottles will be available and can be refilled from onsite breathable air compressors and air reservoirs. A thyroid blocking agent, Potassiun Iodide (KI), is made available to personnel in the CPSES Emergency Organiza tion. 8-2 e~ C' REVISION 3 MAY 21,1982 _ _ _ .~.,,- - ._-- .,_ -. - -- __
~-- - _ _ ., _ _ . - -
CPSES/EP l 8.1.4 PERSONNEL ACCOUNTABILITY Each Station supervisor or the senior individual onsite from his group is responsible for accounting for all persons working in or visiting with his group. Each emergency response facility manager is responsible for accounting for the personnel in their facility. Accountability is determined for each group and reported to the Emergency Coordinator in the event of an Alert, Site Area or General Eme rgency. This process shall be accomplished in accordance with Procedure EPP-209, " Personnel Accountability" and should not require more than 30 minutes to complete. Security personnel, with the aid of their computer, shall be responsible for continuously accountina for individuals thereafter. 8.1.5 PERSONNEL MONITORING Personnel monitoring is the responsibility of the Radiation Protection Section. They shall be supported by the Chemistry / Environmental Section. A TLD reader is available in the EOF in order to maintain up-to-date exposure information on individuals durina an emergency. Personnel exposure records are also available in the EOF. Equipment and personnel are available at the NOSF to check individuals for contamination if suspected. The NOSF also has decontamination facilities available if any contaminated individuals are encountered. 8.1.6 EMERGENCY RESPONSE TIME The time estimate for evacuating the site is projected to be 58 minutes. Justification for this time estimate is provided by the discussion and formula in Section 15.0, Appendix M. 8.1.7 CONTROL OF PUBLIC ACCESS During normal operations, Security shall control access to the Station. The public access road to Squaw Creek Park and Reservoir 8-3 b REVISION 3 MAY 21,1982
- - _ _ - , _ - _ = _ - - , - - .. ... - -
CPSES/EP shall be controlled by Squaw Creek Park, Inc. There will be no direct access to the Station from the reservoir or park. For energency operations, Squaw Creek Park, Inc. shall evacuate the park and relinquish access control to Security. The Security organization may be augmented by State or local law enforcement agencies, as required. 8.2 0FFSITE PROTECTIVE ACTIONS
~
The Texas Department of Health is the lead agency in Texas responsible for of fsite protective actions involving emergency conditions at nuclear power facilities. State and local law enforcement asencies are responsible for controlling access to the 10 mile EPZ. Offsite protective actions are based on recommendations from the CPSES Emergency Coordinator to State and county officials. Instructions to the public regarding implementation of protective actions shall be provided by the county and State officials via the EBS network. Previously prepared messages intended for the public shall be released to the news media by the county officials in conjunction with the EBS announcements. These messages are contained in the county Emergency Plan procedures and are consistent with the CPSES Emergency Action ! Level classification scheme. Specific guidance for notification, evacuation, access control, l control of public water supplies, control of distribution of affected
agricultural products, and evacuation routes is available in Anoendix l
7 of the Texas Emergency Management Plan and the local county plans. Evacuation time estimates for the surrounding population have been developed by CPSES and are provided in Section 15.0, Appendix N. 8.2.1 EMERGENCY PLANNING ZONES The Emergency Planning Zones (EPZ's) are defined as those areas for I which planning is needed to insure that prompt and effective actiore can be taken to protect the public in the event of an accidental release of radioisotopes. The Ingestion Pathway EPZ, 50 mile-radius, are divided into 16 equal sectors (22.5 degrees each) so that in an emergency only those affected sectors need be addressed. The Plume Exposure EPZ and the Plume Exposure EPZ, 10-mile radius, is also divided into concentric circles of one mile increments with the plcnt at the center. Refer to Appendices F and G for maps of the CPSES EPZ. 8-4 O REVISION 3 MAY 21,1982
CPSES/EP Responsibility for notification of the population within the affected l[) sectors in an emergency lies with the local authorities and is outlined in each county's Emergency Ooerations Plan. The Emergency Coordinator provides to the State and local authorities the status of the emergency and recommends protective actions to be taken. Once the local authoritiec have decided that protective actions are to be taken the entire population within the affected sectors of the EPZ must be notified in a reasonable time frame. Notification of the public is the responsibility of local government. The notification system is described in Section 3. Protective actions recommended to the county and State officials are based on the guidelines expressed in the EP A " Manual of Protective Action Guides" (EPA-520/1-75-001); "Public Protection Strategies for Potential Nuclear Reactor Accidents: Sheltering Concepts with Existing Public and Private Structures" (SAND 77-1725), Sandia Laboratory, and
" Examination of Offsite Radiological Emergency Measure for Nuclear Reactor Accidents Involving Core Melt" (SAND 78-0454), Sandia Laborato ry.
8-5 . h REVISION 3 MAY 21,1982
CPSES/EP
*ir D 9.0 RADIOLOGICAL EXPOSURE CONTROL To ensure proper radiological exposure control is maintained even during emergencies, there are tuo Radiation Protection Technicians on site 24 hours per day, 7 days per week. Routine TLD processing is done in the OSC; however, a manual processor is maintained at the Emergency Operations Faci),ity along with another terminal to the radiation records management system.
For emergency conditions, the procedure EPP-305 " Personnel Dosimetry for Emergency Conditions", is utilized. This procedure specifies the responsibilities and actions of the Radiation Protection Engineer and his section regarding the use of high-range dosimeters, the processing frequency of dosimetry and the criteria which allows emergency personnel to receive a radiation dose in excess of the limits set down in 10 CFR 20. Unless a life saving or urgent plant emergency necessitates over-exposure, all emergency actions shall be performed so as not to exceed the exposure limits established in 10 CFR 20. Radiation Protection procedures governing the frequenc' of dosimeter evaluation and maintenance of exposure records exist 'or routine operations. These procedures discuss the proper use of self-reading dosimeters and establish the frequency and criteria for TLD evaluation. 9.1 EMERGENCY EXPOSURE CRITERIA The emergency exposure criteria to be used at CPSES are those ,
recommended by the National Council on Radiation Protection and Measurements and are published in the NCRP Report No. 39, " Basic Radiation Protection Criteria." The provisions of the guidance shall be followed and the dose limits held to the lowest practicable level.
Only the Emergency Coordinator with the concurrence of the Radiation Protection personnel can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. For life-saving actions such as searching for and removing injured persons, or entering contaminated areas to prevent conditions that would probably injure numbers of people: l
a. Rescue personnel should be CPSES volunteers or professional i rescue personnel.-
l 9-1 (h l i REVISION 3 MAY 21, 1982
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CPSES/EP
b. Rescue personnel should be familiar with the consequences of exposure.

c. Women capable of reproduction should not take part in these actions.

d. Other things being equal, volunteers above the age of 45 should be selected. .

e. Planned dose to the whole body shall not exceed 100 rems.

f. Internal exposure should be minimized by the use of the best available respiratory protection and contamination should be controlled by the use of available protective clothing.
, g. Normally, exposure under these conditions shall be limited to once in a lifetime.
h. Persons receiving exposures as indicated above should avoid procreation for a period up to a few months.
For actions in less urgent emergencies where it is desirable to enter a hazardous area to protect facilities, elfminate further escape of e f fluent. 5, or to control fires:
a. Persons performing the planned action should be CPSES volunteers familiar with exposure consequences.

b. Women capable of reproductiou shall not take part.

c. Planned whole body dose shall not exceed 25 rems.

d. Planned dose of hands and forearms shall not exceed 100 rems.

e. Internal exposure shall be minimized by respiratory protection and contamination controlled by the use of protec .ive clothing.

f. Normally the action shall be limited to once a life time.
9-2 REVISION 3 MAY 21, 1982
t CPSES/EP i O' 9.2 CONTAMINATION CONTROL The results of onsite and offsite contamination surveys, taken in accordance with procedure EPP-303, " Emergency Radiological Surveys," ! shall be used as the basis for determining and posting contaminated l areas. Access control, to contaminated areas, shall be handled in accordance with CPSES Radiation Protection Section procedures. The release of contaninated areas shall be determined based on survey results and carried out in accordance with CPSES Radiation Protection Section procedures. Contamination control of drinking water and food supplies shall be handled in accordance with CPSES Radiation Protection Section procedures. 9.3 DECONTAMINATION Decontanination of contaminated personnel will be under the direction of the Radiation Protection Section and will be performed in accordance with the procedure EPP-307, " Radiological Monitoring of Site Evacuees". This procedure prescribes the limits at which decontamination is deemed necessary, lists decontamintion methods and . techniques and the actions to be taken in the event of suspected internal contamination. l The plant decontanination facility, figure 9.1, is located on ! elevation 810' at the normal radiological access control point in the !
! Turbine Building adjacent to the Radiation Protection office. An
j. additional decontamination facility, figure 9.2, is located at the l nearsite EOF for use in emergency situations.
t l The decontamination of personnel, equipment, or areas will be !' dependent on the conditions present at that time, and will be directed to minimize personnel exposure both' to the contaminated person and to the person performing the decontamination. Radiation Protection procedures for routine operations list the methods, limits and precautions necessary for decontamination activities. These procedures shall also be referenced for area posting and material release requirements. - l . 9-3 l 0 REVISION 3 i MAY 21,1982 I
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CPSES/EP During an emergency, areas of the station which are normally G unrestricted access may become contaminated such that they become restricted, access areas. Radiation Protection personnel will monitor the station and make changes as necessary during the course of the eme rgency. If the immediate area around the station should become contaminated, then a restricted area access point may be established at the EOF. The decontanination facility at the EOF would then be used for personnel leaving the station who are contaminated. Decontamination of equipment and areas of the Station wil1 be performed as the emergency condition permits with priority given to equipment or areas essential to recovery of the station to a safe condition. Contaminated areas and equipment shall be classified as such when the levels prescribed in the radiation protection procedure concerning area and equipment decontamination are exceeded. 9.4 RADI0 ACTIVE WASTE Radioactive waste generated or accumulated by the hospital, ambulance or other emergency personnel may be brought to the EOF for storage. As conditions permit, this radioactive waste should be returned to the station for processing. i 9-4 Q i REVISION 3 MAY 21,1982 l l
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REVISION 3 MAY 21, 1982
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\ CPSES/EP Figure 9.2 Emergency Operations Decontamination and First Aid Facilities in the Nuclear Operations Support Facility Personnel Exam and Treatment Shower I
( Exit Corridor ( Entry
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.A Cont. > Contaminated Laundry [3 - -Undressing Area . s/8 ^8 < 4 s, / s' #
Decontamination Emerg. /y - Showers Storage N fl First Aid /N Toilet
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Toilet - -- 1 l , Clean Stor. . Change Room I L*""d#7 G REVISION 3 MAY 21, 1982 1
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CPSES/EP 10.0 MEDICAL AND PUBLIC HEALTH SUPPORT (O ;/ 10.1 MEDICAL TREATMENT As discussed in Section 1.3 two local hospitals are available for accepting injured persons from CPSES. In conjunction with these hospital arrangements, Texas Utilities Generating Company has contracted with Radiation Management Corporation (RMC) to provide expertise, facilities, and equipment to assure a comprehensive emergency medical assistance program. RMC will assist in the _ .,' specification of facilities at the local hospital, training of personnel, and conduct of drills. Capabilities at the University of Pennsylvania Hospital in Philadelphia include a fully equipped radiosurgery suite, reverse isolation units, facilities for white cell transfusion, bone marrow transfusion and chromosome analysis. Medical consultation is available from specialists in a variety of related disciplines. Hood General Hospital serves as the local support hospital for contaminated victims, providing gross decontamination, life saving activities, and patient stabilization. In the event the victim requires more definitive evaluation and treatment, the individual may be sent to the RMC facilities at the University of Pennsylvania Hospital in Philadelphia. Additional support provided by RMC includes the around-the-clock, seven day per week availability of expert consultation and services of a Radiation Emergency Medical (REM) Team, consisting of a licensed physician and a certified health physicist to respond to an accident victim at CPSES as requested by TUGCO. RMC will provide the services of their Bioassay Laboratory and Whole Body Counting Facility if requested. This hospital also serves as a back up to Hood General Hospital. - The Marks English Hospital in Glen Rose is not prepared to handle radiologically related injuries from CPSES; however, the facilites may be utilized for non-radiological injuries. Since no special services are required of the Marks English Hospital staff, a letter of agreement is not required. Letters-of-agreement with Hood General Hospital and the Radiation Management Corporation are included in Section 15.0, Appendix H. l 10-1 kb) REVISION 3 MAY 21,1982
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CPSES/EP t 10.2 MEDICAL TRANSPORTATION A company ambulance is available to CPSES to transport injured personnel, who may also be radiologically contaminated, to the appropriate medical facility. As discussed in Section 1.3, agreements with local ambulance aervices supply back-up assistance as needed. Protective clothing, shielding and dosimetry requirements for transportaing injured and contaminated victims are described in the Emergency Plan Procedure, EPP-308, " Transporting of Contaminated Injured Personnel". 10.3 FIRST AID The first aid station for CPSES is located on elevation 810' of the Turbine Bulding across the hallway from the Radiation Protection office. The station is equipped with standard first aid supplies such as bandages, splints, non-prescription medications, first aid manual, and a stretcher. First aid kits, stretchers, and eye-wash stations are also located throughout the plant at appropriate locations. First aid treatment facilities and equipment are also maintained in the NOSF. 10-2 O REVISION 3 M AY 21,1982
CPSES/EP f.T 11.0 RECOVERY AND REENTRY W Once energency conditions have subsided, and the situation is no
-longer considered a threat to onsite personnel or the general public, efforts shall be initiated to restore the affected unit (s) to full operation or place the affected unit (s) in a long-term safe shutdown condition until full operation can be resumed. The scope of these efforts is dependent upon the severity of the emergency, ranging from a simple close-out to a full-scale mobilization of personnel and resources to support a long-term recovery effort. If a recovery effort is deemed necessary, the CPSES Recovery Organization shall be established to ensure that personnel and resources are properly applied to that effort.
The transition from the CPSES Emergency Organization to the CPSES Recovery Organization is dictated by the severity of the emergency conditions experienced onsite and offsite. Once the designated Emergency Coordinator has established the fact that the emergency conditions have subsided, he and other appropriate TUGCo personnel shall assess the need for initiating a recovery effort. Whether it is i decided that the event should be closed out or that the CPSES Recovery Organization should be established, this decision shall be discussed with, and agreed to and approved by, the appropriate TUGCo management personnel. The appropriate TUGCo management personnel, who shall be involved in this decision-making process, are shown in Table 11.1. For an Alert or higher EAL, the State and county emergency organizations shall be notified prior to closing out the event or
entering the recovery phase. In all cases, the NRC shall be notified of the decision.
If established, overall technical direction and control of the CPSES Recovery Organization is assumed by the Recovery Manager. The CPSES Recovery Organization absorbs the existing CPSES Emergency Organization and management.of all activities from the EOF is assumed from the Emergency Coordinator by the Recovery Manager. The Emergency Coordinator shall continue to direct the Emergency Organization and Emergency Organization personnel should continue functional assignments. The Coordinator shall inform the supporting emergnecy response organizations of the change in Station status and of the CPSES organizational transition. Procedure EPP-215 " Recovery and Reentry" delineates the requirements and actions to be taken for recovery phase activities, including the transition to the CPSES 11-1 LY s REVISION 3 MAY 21,1982 _ n_ _. . .-wmw-~-------- . -- - - - - - - m -C_- _ J '2 / .- _ na.,-
-._----.x.,m CPSES/EP Recovery Organization, and for personnel reentry into evacuated onsite Q
areas. Recovery operations include the evaluation of historical and real-time data and reports, the selection of the proper corrective action and restoration activities, and the acquisition of the equipment and personnel to accomplish those activities. Reentry into the environs of the Station by selected personnel is one of the most important sources of information available to the CPSES Recavery Organization. These activities should aid in ascertaining the resources, manpower and recovery actions necessary to restore the stat 133 to operational status. The Emergency Coordinator has the responsibility for authorizing reentry into a previously evacuated area. Reentries shall be made in accordance with the criteria established in Procedured EPP-215,
" Recovery and Reentry", and the exposure guidelines established in Procedure EPP-305, " Personnel Dosimetry for Emergency Conditions".
This procedure provides specific instructions and criteria for exposure control and, if necessary, a planned over-exposure. All efforts shall be made to keep exposures as low as reasonably achievable ( ALARA). The decision to deescalate or close-oute the activities of the CPSES Recovery Organization shall be made with the concurrence of the Recovery Manager and the Emergency Coordinator, and the approval of the Vice-President, Nuclear. The decision made may be based on a number of criteria, such as:
a. Completion of all corrective action or restoration activities.

b. Availability of the affected unit (s) to resume power operation.

c. Reduced need for specialized talents and resources to perform recovery activities.
I1.1 RECOVERY ORGANIZATION The CPSES Recovery Organization is composed of both onsite and offsite personnel. Corporate and contract personnel are utilized as needed to expand the capabilities of onsite personnel. Since the magnitude of 11-2 O REVISION 3 MAY 21,1982
CPSES/EP
,,g any recovery effort is dependent upon the scope of the event the N) CPSES Recovery Organization staffing requirements are difficult to predict in advance; therefore, this Plan only predesignates certain management level positions in the CPSES Recovery Organization. The managers form their respective groups as they deem appropriate to deal with the recovery effort.
The CPSES Recevery Organization chart is shown in Figure 11.1. 11.1.1 RECOVERY ORGANIZATION - JOB FUNCTIONS 11.1.1.1 Recovery Manager The Recovery Manager is responsible for directing the actions of the CPSES Raccvery Organization and for restoring CPSES to a fully operational status. The Manager, Nuclear Operations is the principal Recovery Manager. In his absence, the Vice President, Nuclear or a designated member of senior management may serve as the Recovery Manager. The responsibilities assigned to the Emergency Coordinator in Section 1.2.1.1 are transferred to the Recovery Manager when the recovery phase begins. This shall ensure the continuity of resources, communications and other activities initiated by the CPSES Emergency Organization. 11.1.1.2 Emergency Coordinator During recovery operations, che Emergency Coordinator shall retain - control of the Emergency Organization and shall report to the Recovery Manager. His primary responsibilities include:
a. Maintaining a liaison between the Recovery Manager and the Dsergency Organization.

b. Coordinating onsite and offsite radiological monitoring and dose assessment activities.

c. Advising the Recovery Manager concerning Station operations, public information releases and protective action recommendations for the public.
l 11-3 ea 2) l REVISION 3 MAY 21,1982 w-_.--..-.-, - . . - . - . -,- _ ,.
CPSES/EP 11.1.1.3 Operations Support Operations Support personnel are responsible for analysis and development of plans and procedures in direct support of operations with the objective of restoring the Station to operational status. Their prime responsibilities include:
a. Provide direct support to shif t operations.
1
b. Analyze instrument and control problems and develop modification and repair plans.

c. Analyze conditions and develop guidance for shift operations i personnel regarding core protection.
1 l d. Develop out-of-normal and emergency procedures for operations suppor t. I 11.1.1.4 Technical Support Technical Support personnel are responsible for the following:
a. Determine the need for and provide engineering and technical specialists to support other managers as required.

b. Assure that design and construction activities are adequately staffed and equipped to provide tLnely support.
c. Provide direct contact between CPSES and others on administrative matters.
d. Direct, coordinate, and approve all engineering, design and construction activities conducted onsite during the recover phase.

e. Develop any required modifications for radwaste systems in support of recovery operations.

f. Provide expertise for Station repair and modification in support of mechanical and electrical problems.
11-4 O REVISION 3 MAY 21,1982
CPSES/EP g'. Provide qualified personnel to augment repair and damage control ('/ 3 teams. 11.1.1.5 Corporate Office Support Texas Utilities Corporate office personnel augment the CPSES Recovery Organization and support recovery activities as requested by the Recovery Manager. The Corporate Purchasing and Public Information departments shall support the CPSES Recovery Organization and assist in procuring of services and equipment and disseminating information to the public. Refer to Section 1.2.3 of the Plan for details. 11-5 l V.) l l REVISION 3 MAY 21, 1982 L . , . , , . . _ . , - . . _ - -_. ~ = ,--,,, ,,, --n.,--_,---n m
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CPSES/EP TABLE 11.1 , l DECISION-MAKING PROCESS FOR EVENT CLOSE-OUT OR TRANSITION TO RECOVERY PHASE l Event Designated Other TUCCO Recommended Severity Emergency Required TUCCO Approval Offsite (EAL) Coordinator Decision-Makers Authority Notifications i i I Unusual Event Shift Supervisor Manager, Plant Opera- Manager, Plant None Requited g tions Operations 'l I Alert TSC Manager Manager, Nucler Opera- Manager, Plant State, Counties tions Operations Manager, Plant Opera-tions l' Site Area Emergency Coor- Manager, Nuclear Op> s- Vice-President, State, Counties
; Emergency dinator tions; Vice-President, Nuclear j Nuclear h
General Emergency Emergency Coor- Manager, Nuclear Opera- Vice-President, State, Counties dinator tions; Vice-President, Nuclear
; Nuclear i + ,
REVISION 3 MAY 21,1982 I
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I CPSES/EP f l FIGURE 11.1 I l l RECOVERY ORGANIZATION I
! RECOVERY I
MANAGER I i i F O N EMERGENCY OPERATIONS TECHNICAL SUPPORT CORPORATE OFFICE Q COORDINATOR SUPPORT SUPPORT y l
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'l i EMERGENCY ORGANI7ATION . e REVISION 3 h MAY 21,1982
CPSES/EP s ,_ / 12.0 EXERCISES AND DRILLS Exercises are conducted to evaluate the integrated capability and a major portion of the basic elements of the emergency response. Drills are conducted to develop and maintain key skills, to evaluate segments of the overall emergency response and to periodically confirm the availability and operability of emergency equipment. De ficiencies identified as a result of these exercises and drills shall be corrected. , As soon as practicable after an exercise or drill, a critique shall be held to identify strengths and weaknesses exposed during the activity. A formal evaluation should result from the critique. Procedure EPP-104, " Emergency Preparedness Drills and Exercises", provides guidelines for developino, conducting, evaluating and documenting emergency preparedness drills and exercises and the responsibilities for implementing this procedure. 12.1 EXERCISES To adequately test the Emergency Plan and to familiarize personnel with their duties and responsibilities, an annual radiological emergency preparedness exercise will be performed at CPSES. The exercise will involve emergency situations based upon a preplanned scenario developed in accordance with Procedure EPP-104. The annual exercise shall include the mobilization of TUGCO, State and local personnel and resources to the extent that the adequacy of the integrated emergency response capability can be verified. Critical communications links between participating organizations shall also be tested. The exercise scenario shall be varied from year to year to ensure that all basic elements of the various emergency plans and emergency organizations associated with CPSES are tested within a five-year period. The exercise scenario shall include provisions to start at least one exercise between the hours of 6:00 p.m. and midnight, and another between the hours of midnight and 6:00 a.m. within a six year period. Some exercises should be unannounced. Selected individuals will be chosen as observation team members. The observation team members shall observe and record the actions of the CPSES Emergency Organization and the performance of the individual members. At the conclusion of the exercise, a critique shall be held, in which the reports from the observers are reviewed and discussed. 12-1 O_ REVISION 3 MAY 21, 1982 n, ,
CPSES/EP A news media orientation shall be conducted in conjunction with the G annual exercise to inform the media of the emergency preparedness program and the purpose of the exercise at CPSES, provide information concerning CPSES and its function and dispell any rumors. 12.2 DRILLS Drills for testing, developing and maintaining skills in particular areas shall be conducted periodically. In some areas, practical drills shall be used to evaluate personnel and allow for '" hands on" training. The drills should follow preplanned scenarios developed to I thoroughly test the response of the personnel involved. State personnel should periodically participate in the radiological monitoring and Health Physics drills. The following drills are
! required:
12.2.1 COMMUNICATICN DRILLS The communication links between CPSES, DPS in Whco and the Hood County and Somervell County centers shall be tested monthly. Communications between CPSES, and State and Federal agencies involved in the i ingestion pathway response shall be tested quarterly. Communications between CPSES, the State and local emergency operations centers, and i the radiological monitoring teams shell be tested annually. I Communication drills shall also include the aspect of understanding the content of messages. f 12.2.2 FIRE DRILLS The members of the onsite fire tema shall participate in quarterly drills and the annual exercise. Drills shall be conducted in accordance with the CPSES Technical Specifications. The local county volunteer fire departments should participate in either the annual exercise or one of the periodic drills. 12.2.3 EMERGENCY MEDICAL DRILLS l Onsite personnel who are assigned to the Emergency Repair and Damage Control Group shall receive annual instruction in handling injured contaninated individuals. Offsite ambulance and medical support i services shall participate in an annual drill or the annual exercise. l 12-2 O REVISION 3 MAY 21,1982
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(~' 12.2.4 RADIOLOGICAL MONITORING DRILLS Station personnel who are assigned to the radiological monitoring i teams shall participate in annual drills which will involve responses to all aspects of environmental monitoring, both on and offsite. These drills shall include collection and analysis of all sample media (e.g. , water, vegetation, soil and air), and provisions for communications and record keeping. 12.2.5 HEALTH PHYSICS DRILLS Health Physics drills shall be conducted semi-annually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment. Analysis of inplant liquid samples with actual elevated radiation levels including use of the post-accident sampling system shall be included in Health Physics drills on an annual basis. 12.2.6 REPAIR AND DA!EE CONTROL Personnel who are assigned to the Emergency Repair and Damage Control Group shall participate in annual drills which involve response to various scenarios concerning repair or recovery of damaged equipment and plant functions. The annual drill may be conducted as part of the annual exercise. 12.3 SCENARIOS i Scenarios shall be developed to provide a mechanism with which to effectively test and evaluate the CPSES emergency preparedness program. These scenarios should allow free play for decision-making and shall include the following minimum criteria:
a. The basic objective (s) of each drill and exercise and j appropriate evaluation criteria;

b. The date(s), time period, place (s) and par; aipating l organizations;

c. The simulated events; 12-3
,f 3 REVISION 3 MAY 21, 1982 m.m _ . _ - . -- - =- .m-___ st_
, CPSES/EP
d. A time schedule of real and simulated initiating events;

e. A narrative summary describing the conduct of the exercises or drills to include such things as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, depicyment of radiological monitoring teams, and public information activities; and

f. A description of the arrangements for and advance materials to be provided to official observers. -
i 12-4 O REVISION 3 MAY 21,1982
CPSES/EP
\
f~\ ' S./ 13.0 RADIOLOGICAL EMERGENCY RESPONSE TRAINING All CPSES personnel and visitors, including those onsite on a temporary basis or in a training status who will be unescorted in the plant, shall receive an orientation on the CPSES Emergency Plan to ensure their safety in an emergency. Station personnel shall be kept informed of changes in the Emergency Plan and Emergency Plan Procedures as appropriate, by annual retraining or as directed by the Manager, Plant Operations. Persons with specific duties during an emergency shall receive training appropriate to their respective assignments. The responsibility for coordinating their training is that of the Director, Nuclear Training. Retraining shall be conducted annually. 13.1 EMERGENCY COCRDINATOR TRAINING Shif t Supervisors along with members of the Station management staf f who may serve as the Emergency Coordinator shall receive training in the CPSES Emergency Plan and their assingned duties and responsibilities. 13.2 RADIOLOGICAL MONITORING TRAINING This trsining shall be given to Station personnel who are required to perform surveys during an emergency. It includes instruction in the selection and use of survey instruments and air sampling equipment and in re-entry criteria. Selected personnel shall also receive training in the use of the computer-based and manual methods of dose a s ses sment. 13.3 FIRST AID TRAINING Selected CPSES personnel shall attend Red Cross Multi-Media or equivalent first aid training to ensure that first aid qualified personnel are always available at the site. 13.4 FIRE CONTROL A training program for the plant employees who serve on the fire fighting teams shall be coordinated by the Director, Nuclear Training. This course shall cover methods and equipment for fighting various 13-1 r , s REVISION 3 MAY 21,1982 _-w
-. . . v -., _
g,
CPSES/EP (b) ' types of fires that could occur on the site. Appropriate emphasis will be placed on the radiological aspects of fire fighting. 13.5 REPAIR AND DAMAGE CONTROL The training program for Station employees who serve on the Emergency Repair and Damage Control (ERDC) Group is coordinated by the Director, Nuclear Training. This training shall cover damage control equipment and techniques, procedures, and station equipment layout.' The ERDC nembers shall also be trained on radiological protection, station safety and first aid. 13.6 OFFSITE GROUPS Offsite groups such as fire departments and rescue and ambulance services that participate in emergency preparedness and response activities shall receive instructions as appropriate to ensure that they are familiar with the CPSES Emergency Plan, general site layout, and their expected response actions in the event of an incident. Retraining to ensure emergency preparedness is conducted on an annual basis. 13.7 OFFSITE MEDICAL PERSONNEL Selected staff members from the offsite medical facilities shall receive training concerning medical aspects of radiological injuries on an annual basis. 13.8 EMERGENCY COMMUNICATIONS PERSONNEL CPSES personnel designated as telephone operators and communicators shall be trained in the use of CPSES communications equipment, the techniques of transmitting and receiving emergency messages, and the maintaining of communications log books. 13.9 EMERGENCY ORGANIZATION PERSONNEL All CPSES Emergency Organization personnel not covered in Sections 13.1 through 13.8 shall receive training according to their areas of assigned responsibility. This training shall be conducted annually and will cover such it. ems as use of the TSC equipment for those assigned to the TSC. 13-2 () l REVISION 3 MAY 21, 1982 L .
, . . . . -- ...;_ ._ . _-~ &. _ __ _ m . _m. . . ~ . < .. m . m .- . .~ m m m m z eaum m s : .-- CPSES/EP Ik- 13.10 EMERGENCY PLANNING PERSONNEL CPSES personnel involved in emergency planning activities should attend formal training courses to maintain and improve their proficiency in all facets of emergency planning. The FEMA Radiological Accident Assessment Course, courses offered by Oak Ridge and participation in seminars, work shops and other utility erargency preparedness drills and exercises may be used for this training. , 13-3
.m ' .. ) .
REVISION 3 MAY 21, 1982
a.w -
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14.0 RESPONSIBILITY FOR THE PLANNING EFFORT: DEVELOPMENT, PERIODIC REVIEW AND DISTRIBUTION OF THE EMERGENCY PLANS The Manager, Plant Operations, has the overall authority and responsibility for radiological emergency response planning. The Station Operating Review Committee is responsible for the annual review of the execution of the Emergency Plan in the annual exercise. The Emergency Planning Coordinator updates the Emergency Plan and Emergency Plan Procedures as needed and ensures that corrective actions identified during the exercise critique, periodic. reviews and surveillances are Laplemented. After each testing of the CPSES Emergency Plan, a critique will be held which should be instrumental in assuring that the Emergency Plan is an effective and viable document. In addition, an independent review of the Emergency Plan and Procedures shall be conducted each twelve months. This also includes reviews of emergency preparedness training, drills, exercises and equipment. These reviews shall be documented and the documentation shall be retained for a period of five years. This review is the responsibility of the Corporate Health Physics Supervisor. Copies of the CPSES Emergency Plan and Emergency Plan Manual shall be distributed to individuals responsible for emergency planning concerning CPSES and authorized by the Emergency Planning Coordinator. These documents shall be assigned a control number. Revisions are issued in accordance with CPSES procedural requirements to holders of
controlled documents to ensure these individuals are in possession of up to date manuals. The Procedure EPP-203 " Emergency Notification and Communications" shall be reviewed quarterly to update the call lists.
The Emergency Planning Coordinator is a Health Physicist in the Radiation Protection Section. He is responsible and has the authority to coordinate the planning effort with all supporting agencies. In addition to maintaining the CPSES Emergency Plan and Emergency Plan Procedures, he is responsible for planning and coordinating exercises and drills, for evaluating equipment needs and for identifying and working with the training department to develop Emergency Plan related training. i 14-1 1 l l') REVISION 3 I MAY 21, 1982 L
a_._~- n - - . . ~ - _ . ......--...-a,----. .--ma. - r - m
. CPSES/EP (h
15.0 APPENDICES A. CPSES Shift Crew Chart B. Time / Distance / Dose (Thyroid) Curve for a LOCA condition at CPSES C. Time / Distance / Dose (Whole body, Gamma) Curve for a LOCA condition at CPSES - D. Time / Distance / Dose (Whole body, Total) Curve for a LOCA condition at CPSES E. CPSES Site Map F. CPSES 0 - 10 miles
1. Demographic Information

2. Area Map G. CPSES 10 - 50 miles H. Letters of Agreement J. List Emergency Kit Equipment and Supplies List K. List of Emergency Plan Procedures M. CPSES Evacuation Time Estimates and Staffing Evaluations N. EPZ Evacuation Time Estimates P. Cross Index to NUREG-0654 I
Q. Definitions and Acronyms l R. Westinghouse Electric Corp. , Water Reactor Div. , Emergency l Response Plan l Note: The letters "I," "L," and "O" are not used as appendix designators. i
;S 15-1 l
REVISION 3 MAY 21, 1982 i
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l 1 REVISION 3 MAY 21, 1982
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4 CPSES/EP
11. With two units licensed to operate and one or both operating, each shift crew shall have at least eight members, including one Shift Supervisor, one Assistant Shift Supervisor and three USNRC Licensed Operators.
l ( l ,i A-3
.gT.f O .i REVISION 3 MAY 21, 1982
_.u.--.......~., .a a, , - .. - - - - .- _ . . . - CPSES/EP C.s) Table A.1 MINIMUM SHIFT CREW COMPOSITION
}! ODE "!*IT LICENSED TO OPERATE UNIT 1 UNIT 1 AND 2 ONE OR BOTH UNITS 1 S. S. 1 S. S.
IN MODE 1, 2, 3, or 4 1 Ass't. S. S. 1 Ass't. S. S. 2 R. O. 3 R. O. 2 A. O. 3 A. O. TOTAL 6 8 EOTH UNITS I!: 1 S. S. 1 S. S. MODE 5 OR 6 1 R. O. 2 R. O. 1 A. O. 3 A. O. TOTAL 3 6 POSITION (1) USNRC LICENSE l SHIFT SUPERVISOR - S. S. SRO ASSISTANT SHIFT SUPERVISOR - Ass' t. S. S. SRO REACTOR OPERATOR - R. O. RO AUXILIARY OPERATOR - A. O. NONE (1) Any qualified and USNRC Senior Licensed member of management may be used to satisfy the minimum Shift Supervisor or Assistant Shift Supervisor requirement. Any qualified and USNRC Licensed
individual may be used to satisfy the Reactor Operator
( requirement. [] REVISION 3 MAY 21, 1982
. - - _ . . . _ _~
CPSES/EP O _ APPENDIX B p Time / Distance / Dose (Thyroid) Curve for a LOCA condition at CPSES l l l B-1 i 1 i l. REVISION 3 MAY 21, 1982 l l I
CPSES/LP f THYROID DOSE FOLLOWiNG LOCA Figure B.1 {p 50 - 300 rem 150 ren I i 10 - 5 - 7 d E S D 1 ~ 8 35 5
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REVISION 3 MAY 21, 1982
(l} CPSES/EP APPENDIX C Time / Distance / Dose (Whole body, Gamma) Curve for a LOCA condition at CPSES i C-1 L.' REVISION 3 MAY 21, 1982
I l l CPSES/EP l WHOLE BODY GAMA DOSE FOLLOWING LOCA Figure C.1
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I (?}~ . CPSES/EP t ( APPENDIX D Time / Distance / Dose (Whole body, Total) Curve for a LOCA condition at CPSES i'
~ ;)- ' D-1 i _
l REVISION 3 1%Y 21,1982
_ -.~. _ _ - . _ . - - . - . . . . . ,, CPSES/EP' THYR 0!D DOSE FOLLOWING LOCA fs Hgure B.1 50 - 300 res 150 rem i 10 - 5 - O
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APPENDIX E CPSES Site Map mi E-1 REVISION 3 MAY 21, 1982
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1. Demographic Information Map

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CPSES/EP D (o APPENDIX H Letters of Agreement l l l l l l l l l l ,s Nb l H-1 REVISION 3 MAY 21, 1982 e !' r- - - *** N FT' T~ y srN
HOOD GENERAL HOSPITAL 1310 PALUXY ROAD
P. C. BOX 490 GRANBURY, TEXAS 76048
(.~M ( 3 ) RECEIVED f II APR 2 31992
,, 3.
n. woe rh. -1 egye.w,,n5,3,gp April 20, 1992 Manager, Plant Operations Texas Utilities Generating Company Comanche Peak Steam Electric Station P.O. Box 2300 Glen Rose, Texas 76043
Dear Sir:
The Hood General Hospital herein agrees and assures that the following assistance will be provided to the Comanche Peak Steam diectric Station (CPSES) upon request:
1. The Hood General Hospital shall provide on a twenty-four (24) hour per day basis, personnel and facilitiesfor normal and emergency services to ,.
personnel at CPSES who may be injured or require routine physical examination, whether or not they are radioactively contaminated or overexposed.
2. Hood General Hospital personnel shall participate in site specific exer-cises, drills and training provided for that purpose by TUGCo. The drills and exercises to be followed by a critique and written evaluation.
It .is understood and agreed that: A. TUGCo will assist in the development of detailed emergency procedures l to be followed by the Hospital staff when dealing with a radiologically contaminated or overexposed patient. B. TUGCo will notify the Hood General Hospital as quickly as possible once i it is recognized that assistance from the Hospital may be required. l C. TUGCo will provide technical assistance, radiological monitoring equip-ment and personnel monitoring devices necessary to evaluate the radio-i logical condition of the patient. 1 D. The Hood General Hospital Staff shall include a physician who has l . received training in the handling of radiation accident victims. o E. Hood General Hospital would, on the basis of expert consultation, discharge patients to be transferred to other medical facilities, should the treatment required for radiation injury extend beyond the capa-
bilities of the Hospital .
Cont'd
Hood General Hospital page 2 b
% F. Both parties will coordinate, to the extent possible, all information disseminated to the public regarding the severity and magniture of an incident at CPSES, G. Hood General Hospital will periodically review the status of their plans, procedures, agreements and capabilities which ma; require revision and/or further development; and to conduct drills or exer-cises involving radiolcgical emergency response.
ii. Compensatio'n for the services and facilities of Hood General Hospital shall be paid to the Hospital by TUGCo on the basis of the usual and customary fee for each service required, subject to the following:
1. Hood General Hospital shall provide, under separate cover, to TUGCo a listing of such standard fees for services as are set forth above.

2. As changes are made to these standard fee schedules, updated copies shall be provided to TUGCo prior to implementation.

3. Charges for Hood General Hospital services shall be invoiced to TUGCo following performance of the service. These invoices shall itemize the specific charges, as listed in standard fee schedules, including the date of any charges, the number of man-hours or service units, the type of service provided and identifi-cation, as appropriate, of any patients treated.

4. All charges assessed under this agreement shall be those as listed on standard fee schedules. All other costs including administration, overhead, rent, insurance, office costs, travel costs and payroll costs, except as noted on the fee schedules, shall be borne by the Hospital.

5. Charges for approved modifications and preparation of Hospital facilities for receipt of contaminated patients will be paid by TUGCo, on the basis of the actual cost of the required modifi-l cation and preparations.
l
6. TUGCo sould be responsible, in the case of a radioactively con-i taminated patient, for any damages to, or cleanup of, hospital l facilities resulting from radioactive contamination as a direct result of the handling and admittance of such person prior to his decontam-ination, and for the disposal of contaminated dress-ings, coverings, cleaning materials, etc., resulting from treat-ment of contaminated patients.
The aforementioned agreements and assurances shall continue unless expressly modified in writing to the Manager, Plant Operations, CPSES. This Agreement shall be reviewed annually and updated as appropriate, g Sincerely yours, 1 w f l e S. Langford Administrator JSL/cp l _ _ _ ~_ _ ___.. _ __ _ - _ ,. ~ _ _ _
TEXAS UTILITIES GENERATING COMPANY OFFICE MEMORAND UM To Reviewer May 13, 1982 r;~
, Glen Rose. Texas subject ' Letter of Agreement The letter of agreement with the Granbury Volunteer Fire Department is being re-negotiated and will be added to the plan when it becomes avail-able.
G. Bell HP-EPC GB/ dim l 9 l
..- .------,,----r.__ mm
EDWIN TOMLINSON SHERIFF P. O. Drower H Phone 817/5731123 h 1402 W. Pearl Granbury, Texas 76048 REC E'y Manager, Plant Operations APR 07 gg,L Texas Utilities Generating Company Comanche Peak Steam Electric Station cge.gg,,,p,,a Glen Rose, Texas 76043
Dear Sir:
The Hood County Sheriff's Department herein agrees and assures that assistance shall be provided, in the event of an emergency, to the Comanche Peak Steam Electric Station (CPSES),upon request, as detailed in the Hood County Emergency Operations Plan. Specifically, Hood County Sheriff's Department equipment and personnel shall be made available, as applicable to a specific event, to:
1. Authenticate the notification of an emergency by calling back the agency"which made the initial notification;

2. Notify the key officials as described in the appropriate
" Call List."
3. Activate the warning of Hood County citizens within the ten (10) mile emergency planning zone (EPZ).

4. Provide traffic control and coordinate with the Granbury Police Department and the Texas Department of Public Safety in establishing road blocks within Hood County on roadways at the outer boundary of the 10 mile EPZ. The purpose of the road blocks is to control traffic exiting and prevent traffic entering the affected area.

5. Coordinate with the Granbury Police Department and the Texas e
Department of Public Safety to establish detpur routes, if required, around the affected area within Hood County.
Hood County Sheriff's Department Page 2 It is also understood and agreed that appropriate Hood County Sheriff Department personnel will participate in periodic drills, an annual exercise and site specific emergency response training sessions provided by TUGCO personnel at mutually agreed times and locations. The training sessions shall include as a minimun procedures for communication shall include as a minumum procedures for communication, the CPSES Emergency Plan and the CPSES Emergency Facilities. The aforementioned agreements and assurances shall continue unless expressly modified in writing to the Manager, Plant Operation, CPSES. This agreement shall be reviewed annually and updated as appropriate. Very truly yours,
/
N Hood County Sheriff l l l 1 [
HOOD GENERAL HOSPITAL 1310 PALUXY ROAD
P. O. BOX 490 GRANBURY TEXAS 76048 lcm) -
r- 2 - Irl Phone 573 ?683 C RECEIVED Ft. Worth Ph. 443-0351 gpg p,3 l; ' 7,
, April 20, 1982 C99ANC,t$ M ,d N Manager, Plant Operations Texas Utilities Generating Company Comanche Peak Steam Electric Station P.O. Box 2300 Glen Rose, Texas 76043
Dear Sir:
The Hood General Hospital Ambulance Service herein agrees and assures that the following assistance will be provided to the Comanche Peak Steam Electric Station (CPSES) upon request:
1. Provide ambulance service, including administration of first aid, on a twenty-four (24) hour per day basis to injured personnel at CPSES, whether or not they are radiologically contaminated or overexposed, for transportation to Hood General Hospital or, as required, to other medical facilities.

2. Hood General Hospital Ambulance Service agrees to coordinate the request for back-up ambulance request, if required.
It is also understood and agreed that: A. Should the assistance of the Hood General Hospital Ambulance Service be required at CPSES, they will be notified by the CPSES Emergency Coordinator or designee, who will provide available information regarding the number of injured personnel, their condition and location. B. The Hood General Hospital Ambulance Service may verify the authenticity of the request by calling the CPSES Control Room. C. Unless requested otherwise, on arriving at CPSES the Hood General Hospital Ambulance Service personnel will report to the Security Gate and allow TUGCo Security to escort them to the location of the injured personnel. [ah D. At the location of injured personnel, the Hood General Hospital Ambulance Service personnel shall coordinate actions with the CPSES Emergency Coordinator or designee. Cont'd
.__.m_ -. .. ----- _. _ _ ~ .-_,. _ , _ _ _ .._. _ _ _ _
Page 2 Q E. Should an injured individual requiring ambulance transportation be located in a radiation area, Hood General Hospital Ambulance Personnel shall follow the instructions of the CPSES staff trained in radiation safety for the protection of the Ambulance Service personnel . F. Should it be necessary to transport a radiologically contaminated person, CPSES personnel may take the necessary precatufon's to prevent or minimize the spread of contamination, a member of the CPSES staff trained in health physics snall accompany the injured to the hospital. G. Appropriate Hood General Hospital Ambulance personnel will partici-pate in periodic drills in annual exercise and site specific emergency response training sessions provided by TUGCo personnel at mutually agreed times and locations. The training sessions shall include as a minimum procedures for notification, basic radiation protection, the CPSES Emergency Plan and emergency facilities and site access procedures. The aforementioned agreements and assurances shall continue unless expressly modified in writing to the Manager, Plant Operations CPSES. This Agreement shall be reviewed annually and updated as appropriate. Sincerely, oe S. Langford Administrator JSL/lb l l
O W . ..a - m ; - _ _ .__ - w w..v--- -w -w w -w _-_...%%, wnise-.%
I
.~ :. .> u FRANyfJ{g;, MORE Sheriff [-56'mory) o ); q :ell. .. County i(o:., j /h :,/'
P.O. Box 1000 Phone 817 897 2242 Glen [o'ie[Temis f6043 March 26, 1982 Manager, Plant Operations Texas Utilities Generating Company Comanche Peak Steam Electric Station P.O. Box 2300 Glen Rose. Texas 76043
Dear Sir:
The Somervell County Sheriff's herein agrees and assures that assistance shall be provided, in the event of an emergency, to the Commanche Peak Steam Electric Station (CPSES), upon request as detailed in the Somervell County Emergency Operations Plan. Specifically, Somervell County Sheriff's Department equipment and personnel shall be made available, as applicable to a specific t event, to: l 1. Authenticate the notification of an emergency by calling
back the agency which made the initial notification.
2. Notify the key officials as described in the appropriate
" Call List".
3. Activate the warning of Somervell County citizens within the ten (10) miles emergency planning zone (EPZ).

4. Provide traffic control and coordinate with the Texas Department of Public Safety in establishing road blocks within Somervell County on roadways at the outer bound-ary of the ten (10) mile EPZ. The pu'rpose of the road blocks is to control traffic exiting and prevent traffic entering the affected area.

5. Coordinate with the Texas Department of Public Safety to establish detour routes, if required, around the af-facted area within Somervell County.

6. Provide security of the affected area within Somervell County.

7. Coordinate communication assets with other county agencies and provide backup communication.
It is also understood and agreed that appropriate Somervell County Sheriff's Department personnel will participate in periodic drills, an annual exercise and site specific emergency response training sessions provided by TUCCo personnel at mutually agreed times and locations. The training sessions shall include as a minimum procedures for communication, the CPSES emergency Plan and 't h e CPSES Emergency Facilities. The aforementioned agreements and assurnaces shall continue unless expressly modified in writing to the Manager, Plant Operations. CPSES. This agreement shall be reviewed annually an updated as appropriate. Ver ruly your u w N O I 1932 Frank . Laramore
, Sheriff, Somervell County I (N, w
F4a.
\
l l FJL/vjh L. ___ _ _ _ _ . -. . . . _ . _ _ _ _ . . _ _ _ _
GLEN ROSE-SOMERVELL COUNTY VOLUNTEER FIRE DEPARTMENT P.O. Box 279 Gloo Rose. Texas 7M43 Manager, Plant Operations % Texas Utilities Generatin.g Company Comanche Peak Steam Electric Station APR 12 1902 P.O. Box 2300 %-Why,,p"n a ," Glen Rose, Texas 76043 ~"mm
Dear Sir:
The Glen Rose /Somervell County Volunteer Fire, Rescue and Ambulance Service herein agrees and assures that the following assistance will
be provided to the Comanche Peak Steam Electric Station (CPSES) upon request

l
1. Provide fire-fighting personnel and equipment as necessary to assist the CPSES Fire Brigade in extin.9.uishing fires at CPSES and on adjacent CPSES property.

2. In the event additional manpower or equipment is needed, i
such additional assistance will be coordinated and requested by the Glen Rosc/Somervell County Volunteer Fire, Rescue and Ambulance Service. It is also understood and agreed that: A. Should the assistance of the Glen Rose /Somervell County Fire, Rescue and Ambulance Service be required at CPSES, they will be called by the CPSES Emergency Coordinator l or designee. B. The Somervell County dispatcher may verify the authenticity of the request by calling the CPSES Control Roon. C. Unless requested otherwise, on arriving at CPSES, the Clen Rose /Somervell County Volunteer Fire, Rescue, ll{} and Ambulance Service personnel will report to the l Security Gate and allow TUCCo Security to escort them to the scene of the fire.
GLEN ROSE SOMERVELL COUNTY VOLUNTEER FIRE DEPARTMENT M P.O. Box 279 Glen Rose. Texas 76043 D. At the scene of the fire, the Glen Rose /Somervell County Fire Chief or designee shall coordinate actions with the CPSES Fire Brigade leader or designee. E. Should a fire-fightinc effort be required in a radiation area, personnel shall follow the instructions of CPSES staff trained in radiation safety for the protection of these emergence personnel. It is also understood and agreed that appropriate Glen Rose / Somervell County Volunteer Fire, Rescue, and Ambulance Service personnel will participate in periodic drills, an annual exercise and site specific emergence response training sessions provided by TUGCo personnel at mutually agreed times and locations. The training sessions shall include as a minimum procedures for notification, basic radiation protection, site access procedures and emergency response functions. The aforementioned agreements and assurances shall continue unless i ! expressly modified in uriting to the Itanager, Plant Operations, l CPSUS. This Agreement shall be revieued annually and updated as appropriate. l , Very truly yo s, M' (Principal Party) Clen Rose /Somervell County Fire Chief i () t u__ _ _ _ _ -. . _ . _ _ _ _ _ . __m __
,q rmC 16 December 1977 Mr. Robert J. Gary Executive Vice President 4 General Manager Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 SURJECT: Emergency Medical Assistance Program
Dear Mr. Gary:
l l This confims an agreement between Radiation Management Corporation l (RMC) and Texas Utilities Generating Company, wherein RhC agrees to furnish certain services to nuclear generating stations operated by i Texas Utilities Generating Company. These services comprise a program that is identified by RMC as an Emergency Medical Assistance Program (BIAP) . With regard to Comanche Peak, the EMAP contains the following provisions:
1. Semi-annual review of plant and hospital procedures, equip-ment and supplies; one of these audits will be in conjunction with (6.) below;

2. Wenty-four-hour per day availability of expert consultation on management of radiation accidents;

3. Availability of Bioassay Laboratory for evaluation of radiatior accidents; pg Igu GR 4. Wenty-four-hour-per day access to a Radiation Emergency Iu UII Medical Team consisting of a physician, certified health mgngnomGn Physicist, and technicians with portable instrumentation muHUUUlllDHI to location of accident victim; llfllflllll 5. Availability and access to the University of Pennsylvania facilities and staff necessary to provide definitive evaluatior
.and care of radiation accident victims; unti'rAsn en 6.
sciruce cruira Annual training for the plant, ambulance and hospital personnel who may be directly or indirectly involved in the execution of the radiation medical emergency program; 3508 MARKET STREET PHI DE A. PA 19104 7, preparation of an " accident" Scenario for use as a training aid in a radiation medical emergency drill; w U
m
'.)
Mr. Robert J. Gary rmC 16 December 1977 Page Two
8. Coordination of a radiation medical emergency drill based on the scenario; umpired, video-taped and critiqued by RMC.

9. Submission of two Drill Evaluation Reports; one relating to the observations made at the station, and another relating to observations made at the hospital; and

10. Participation in an annual one-day seminar in Philadelphia on the management of radiation accidents for physicians.
Each plant site may send one person, and each utility company may send one person. TION MANAGBIENT CORPORATION
) h +e _
ge . Linnemann, M. D. P esident REL:FGR:pg i l
- . . . - _ - . . . . _ -_ _- -- -- - - ---- - . - ----= - -
o " Texas Department of Hea t, Robert Bernstein, M.D., F.A.C.P. 1100 West 49th Street Robert A. MacLean, M.D. Commissioner Austin, Texas 78756 Deputy Commiss;oner (512) 458 7111 Professional Services Hermas L. Miller Deputy Commissioner Management and Administration l April 29, 1982 Mr. R. A. Jones Manager, Plant Operations Texas Utilities Generating Canpany Cananche Peak Steam Electric Station P. O. Box 2300 Glen Rose, Texas 76043
Dear Mr. Jones:
The Bureau of Radiation Control, Texas Department of Health is required by the 'lbxas Disaster Act of 1975, as amended, and the Texas Emergency Management Plan to perform advance planning and respond appropriately to accidents within the state. Tab 1 of Appendix 7 to Annex L, Radiological Emergency Response, of the Texas Emergency ' Management Plan provides necessary guidelines, procedures and instructions for emergency situations involving fixed nuclear facility accidents. Contained within the Tab are specific duties, assignments, and responsibilities. Among these are: l o Radiological monitoring within the Plume Exposure and l l Ingestion Exposure Pathways. l o Accident Classification System o Bureau of Radiation Control response levels o Response Team Composition i o Accident Asses'sment o Contamination Survey Techniques o Personnel Monitoring and Decontamination gg o Recovery Frcm an Accident MAY 0 31982 i l '. o Area Decontamination c. C9u. an.e.w.n..pcAx s.nu
c. s, o Trainirg l o Exercises and Drills
.- _- - _ _ _ _ _ _ _ _ . _ . . . .~ . . - - . .
(, . .
. . j_ .,
Texas Utilities Generating Company April 29, 1982 Page 2 Ths Bureau of Radiation Control will respond to emergencies at Comanche Peak Steam Electric Station with sufficient qualified personnel and equipment to fully support local government (s) in its mitigation and recovery effort. The Agency will maintain close liaison with the Texas Utilities Generating Company (TUGCo), utilizing facilities provided by
'IUGCo at its Near Site Emergency Operations Facility. , 'Ihis a6reement shall remain in force until expressly modified in writing by the Chief, Bureau of Radiation Control to the Manager, Plant Operations, Comanche Peak Steam Electric Station; it shall be reviewed annually and updated as appropriate.
Yours truly, M )b David K. Lacker, Chief Bureau of Radiation Control l I _ema_--e umm-.. .%yem
- _ -*.-nmnew .g.,_ % L',4- ,r 3. , ,g,. . Ac t.,w .. eL
TEXAS DEPARTMENT OF PUBLIC SAFETY
,4 ~- 5805 N. LAMAR BLVD. . BOX 4087. AUSTIN, TEXAS 78773 April 5, 1982 JAMES 8. ADAMS ROBER R. 5 LTON DIRECTOR CHAIRMAN * " ' ^*
IsSENE!TS CoM eNE Manager, Plant Operations Texas Utilities Generating Company Comanche Peak Steam Electric Station P. O. Box 2300 Glen Rose, Texas 76043
Dear Sir:
The Texas Department of Public Safety (TDPS) herein agrees and assures that the following assistance will be provided to the Comanche Peak Steam Electric Station (CPSES):
1. In the event of an emergency at CPSES, the TDPS will serve as the primary communication contact and coordinate emergency communications between CPSES and the State of Texas, Hood and Somervell Counties.

2. The TDPS will coordinate with the local law enforcement officials and assist in maintaining traffic control, protecting life and property, establishing road-blocks and alerting and warning persons in the affected area.
It is also understood and agreed that: A. The Texas Department of Public Safety will participate in periodic communication drills and exercises. 1 B. This Letter of Agreement shall not serve to limit any actions of the Texas Department of Public Safety, under the laws of l Texas, to carry out its responsibilities in all areas not j prohibited by law. The aforementioned agreements and assurancis shall continue unless expressly modified in writing to the Manager, Plant Operations, CPSES. I This Agreement shall be reviewed annually and updated as appropriate. Sincerel
. R. Allen, Major RECEIVED Depart 2nent of Public Safety Region VI - Waco APR 06 i.
JRA/mc cgye.c.atgre,,s,p __- -- ._ _......._._._."""*""""*"*"?""_ ~_ __ ~ _ _ _
w ODepartment of Energy Albuquerque Operations Office , . . P.O. Box 5400 F 1 ,. - Albuquerque, New Mexico 87115 B. P.. G.Ei.iENTS Mr. B. R. Clements Vice President Texas Utilities Generating Company M i $ 132 2001 Bryan Tower Dallas, Texas 75201
Dear Mr. Clements:
Please reference your letter dated February 9, 1982, to Mr. Jack R. Roeder of my staff, and the letter from Farman E. Roser, Manager, Albuquerque Operations Office, dated June 3,1977, to tir. R. J. Gary, Executive Vice President and General Manager, of your company. This letter is to provide assurance that the Department of Energy (DOE) will respond to requests for radiological assistance from licensees, Federal, state and local agencies, private organizations or individuals involved in or cogni-zant of an incident believed to involve source, by-product, or special nuclear material as defined by the Atomic Energy Act of 1954, as amended, or other ionizing radiation sources. Assistance as indicated above would be made available to the Comanche Peak Steam Electric Station upon request and pro-vided in consonance with response activities conducted by state, local and
private industry preparedness personnel.
1 Unless the DOE or a DOE contractor is responsible for the activity, ionizing radiation source, or radioactive material involved in an incident, DOE radio-logical assistance will be limited to advice and emergency action essential for the control of the immediate hazards to health and safety. Radiological emergency assistance will be terminated as soon as the emergency situation is under control. Therefore, responsibility for postincident recovery, including further action for the protection of individuals and the public health and i safety, should be assumed by the appropriate responsible Federal, state or l local government, or private authority as soon as the emergency conditions are stabilized. r:s V} 6
> Mr. B. R. Clements 2 Id;M Requests for DOE emergency radiological assistance may be made on a twenty-four hour basis to the Region IV Radiological Assistance Plan Coordinating Office, telephone: (505) 844-4667. . D b atovEki Manager cc:
L. J. Deal, ONS, HQ, EP-34 John Collins, Regional Administrator Region IV, NRC, Arlington, Texas J. D. Winkle, Acting Regional Director Region VI, FEMA, Denton, Texas Dr. Robert Bernstein, Connissioner . Texas Department of Health, Austin, Texas f e 2
J m
*) g, , ~
q
\ 't kh -c -
Manager, T1 tnt Cperations Eu
~
A ril 29, 1982 Texas ComancheUtilitics reak SteamOcncrating 71ectric Stat Fr Comian h [Q- R T.O. Box 2300 Glen Rose, Texas 7601.3
Dear Sir:
Ccuaw Creek Fark, Inc. (CCFI) assistance will be provided to herein comanche agrecs Feak and Steam assures thatStation electric the following): (CPS"r 1.In the event of an emergency at CTfFF, SCFI is recronsible for the evacuation of the Squaw Creek Fark and 2ccervoir and the accountabilit; of all 1. ark visitors.
2. SCFI is responsible for access to e c,uaw Creek Fard and reservoir and for responling to accidents occuring in the i. ark an1 the reservoi:
It is also understood and agreed that:
4. CCFI will coordinate with CFS S personnel th. develorment of written procedures for emergency actions; B. CCTI will make available brochures and emergency information to all park vicitors; C. SCPI may be ree,uired to larticipate.in exercises, irills and site siecific training, and D. TUGCo Cecurity, by request, may assist FCFI in evacuating the park and roscrvoir.
( The aforementione1 agreements ani assurances shall continue unless egressl: l modified in writing; to the Manager, Flant operations, CPTTD. This Agreement shall be reviewed annually and ul dated as apfroiriate. Ve~ ~ ours,
.drsb, e 1.Kt .gc Q. % a.
Roger Crawford, Vicc Frcsident Squaw Creek Park, Inc. l 1 l I.$) l l l l Route 1. Box 66 Granoury. TX 76048
c. _ _ _ _. . - -
.r?.
5;.,) CPSES/EP APPENDIX _J Eraergency Kits Equipment and Supplies List 1 . J-1 yy,
'c -)
REVISION 3 MAY 21. 1982
CPSES/EP 13>3
s Rubber Gloves - Pair Glove Liner - Each Disposable Shoe Covers Caps Hoods Beta Gamma TLD's External TLD's Low Range Dosimeter High Range Dosimeter Dosimeter Charger Chirpers FM Transceiver Spare Battery Chargers Smear Counter - Man.
Plastic Bags - medium /large Signs and Inserts Barricade Rope / Ribbon Stepof f Pads 55 gal Drums Decon Supplies Tape - Roll - Paper Tape - Roll - Duct Portable Lights Batteries Tools II. Field Monitoring Kit Dose Rate Instrument Count Rate Instrument Pancake GM Detector Spare GM Tube NaI Detector Portable MCA Full Face Respirator without Filter Particulate Cannister Sorbent Cannisters Potassium Iodide Air Sampler - Sample Heads J-3 SSJ REVISION 3 MAY 21, 1982 . _ _ _ _ ,_._ _ -_ ; _ _w - --
CPSES/EP f.T's
_,) '
APPENDIX K List of Emergency Plan Procedures
.,s Q)
K-1 REVISION 3 MAY 21, 1982
CPSES/EP 7,, . O .] , Emergency Plan Procedure No.
~
Title Reference EPP-301 Control Roon Assessment of 7.0 Radiological Conditions EPP-302 Of f-Site Dose Calculations 7.0 EPP-303 Emergency Radiological Surveys 7.0 EPP-304 Protective Action Guides 8.0 EPP-305 Personnel Dosimetry for Emergency 9.0 Conditions EPP-306 Use of Thyroid Blocking Agents 8.0 EPP-307 Radiological Monitoring of Site 8.0 Evacuees EPP-308 Transporting of Contaminated Injured 10.0 Personnel - EPP-310 Surveillance of Emergency Supplies 6.6 b REVISION 3 K-3 MAY 21, 1982 . .- _ _ _ _ . _ _ _ _ _ _ , .._ _, ___ _. . ~ .- _ _
= _ . . . - . . - _ , . . _. _ . _._.
S )
~
CPSES/EP APPENDIX M CPSES Evacuation Time Estimates and 1 Staffing Estimates 1 l M-1
< ! *2 '
REVISION 3 MAY 21, 1982 L____. . _ _ _ _ --- - _ - --. ~- - . . - . _ . . _ _ _ . _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _
.. s CPSES/EP V.)
is predicted to be 10,000 persons per hour. Using two traffic lanes and adjusting the lane capacity stated above to a more conservative condition of 20 miles per hour and two persons per car, it is projected that travel time for 1,500 persons will be 31 minutes. Time estimate for evacuating personnel from the Exclusion Area by vehicle is projected to be 57 minutes. Justification of this projection is provided by the following formula and discussion. T(ev) - Td + Tn + Tm + Tt where T(ev) = (57 minutes) Time required to evacuate persons from the Exclusion Area. A typical situation could be notification and evacuation of individuals working on pumps located below Squaw Creek Reservoir Dam. Td = (15 minutes) Time required for the detection of the accident, data analysis, and decision to evacuate. l l l M-3 q) l REVISION 3 MAY 21, 1982 __ m, _ .. _ _ .
CPSES/EP pq:
.) .
Tn = (28 minutes) Time to notify individuals to evacuate affected area. 10 minutes estimated to have boat lake-ready. 18 minutes for actual travel time. Tm = (5 minutes) Time required for individuals to make ready and get under way. Tt = (18 minutes) Travel time required to leave affected area. M-5 O REVISION 3 MAY 21, 1982
CPSES/EP i$~) 20% of employees reside in Cleburne, Stephenville, Tolar and Ft. Worth Actual travel times are: Glen Rose to CPSES - 10 to 20 minutes Granbury to CPSES - 25 to 30 minutes Cleburne to CPSES - 30 to 35 minutes Stephenville to CPSES - 40 to 45 minutes Ft. Wbrth to CPSES - 50 to 55 minutes Therefore the following percentages are used: Tt = 10 minutes - 20% of employees 20 minutes - 20% of employees 9 l 30 minutes - 40% of employees 40 minutes - 10% of employees ; 50 minutes - 10% of employees l l ! M-7 l l bh REVISION 3 MAY 21, 1982
CPSES/EP O
Where Ta = (50 minutes) Activation Time Tn = (10 minutes) Notification Time Tp = (10 minutes) Personnel Preparation Time Tt = (30 minutes) Transit Time for Essential Personnel The Transit Time of 30 minutes was established in a statistical staffing study and supported by contacting several individuals.
Inclement weather (ice storms) would add approximately 30 minutes to the travel time, yielding an activation time of 80 miautes. 1 M-9 h REVISION 3 MAY 21, 1982
- . . . . . . . . . ~ . ~ . .- - . . n . _ - - ---- - . - - - - - - . = ..
CPSES/EP ("} APPENDIX N EPZ Evacuation Time Estimates i 1 1 l l b N-1 REVISION 3 MAY 21, 1982
.__ __ .._..s..,. . . . .
gg A D O' TABLE 2: Summary of Results of Evacuation Times Analysis x . ., .a . x x a a 8 % 81 a 8 e d. a a. e a e a t 38 3a e . a . t
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! SW 0-5 430 236 450 150 gj "
20 19 31 44 56 87M 50 60
]
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15 26 37 46 57 18Ma 50 61 NW 0-1( 1589 873 0 3 " 20 26 33 51 58 Ig 0 0 i i
upper number represents vehicles used by schools @ 20 persons per vehicle
** upper number represents normal conditions; lower, adverse conditions RBISION 3
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CPSES/EP b APPENDIX P Cross Index to NUREG-0654 I i I \ \ P-1 I 1 (%. REVISION 3 ! MAY 21, 1982 i
~
CPSES/EP APPENDIX P CROSS INDEX NUREG-0654, SECTION 11 CPSES EMERGENCY PLAN A-1.a 1.3 A-1.b 1.3 A-1.c 1.0 (Figure 1.1) A-1.d 1.2.11 A-1.e 1.2 A-2.a N/A A-2.b N/A A-3 Appendix H A-4 5.0, 11.1.1.1 B-1 1.2.1 B-2 1.2.1.1 B-3 1.2.1.1 5 B-4 1.2.1.1 B-5 1.2 B-6 Figure 1.1 B-7 1.2.3 B-7.a 1.2.3 i B-7.b 1.2.3 l B-7.c 1.2.3 t I ( P-2 O REVISION 3 MAY 21, 1982 l
CPSES/EP B-7.d 1.2.3
~^
B-8 1.2.4 B-9 1.3, Appendix H C-1.a-c 4.3.3.3 C-2.a N/A C-2.b 6.4 C-3 1.3.2.1, 1.3.3.3 C-4 1.3, Appendix H D-1 2.0, Appendix K D-2 2.0, Appendix K D-3 N/A D-4 N/A E-1 3.0, Appendix K E-2 3.0, Appindix K E-3 3.0, Appendix K E-4.a-n 3.0, Appendix K E-5 N/A E-6 3.0 E-7 3.0, Appendix K F-1.a 1.2 F-1.b 4.0 - F-1.c , 4.0 P-3 l'. REVISION 3 MAY 21, 1982
CPSES/EP F-1.d 4.0 F-1.e 4.0, Appendix K F-1.f 4.0 F-2 4.0 F-3 12.0 G-1.a-d 5.0 G-2 5.0 G-3.a-b 5.0 G-4.a-b 1.2.1.7, 5.0 G-4.c 5.0 G-5 5.0,'12.0 H-1 6.1., 6.2 H-2 6.3 l H-3 N/A H-4 Appendix K H-5.a-d 6.6 H-6.a l H-6.b Appendix K l H-6.c 1.3.2.1, 1.3.3.3 i
H-7 6.6 l
l . H-8 6.6.5 l H-9 6.2 P-4 O REVISION 3 MAY 21, 1982
CPSES/EP H-10 6.6, Appendix K H-11 Appendix J H-12 6.3 1-1 7.0, Appendix K 1-2 7.0 I-3.a-b 7.0, Appendix K I-4 Appendix K I-5 6.6.5 I-6 Appendix K I-7 6.6, Appendix K 1-8 7.0, Appendix K I-9 6.6, Appendix K I-10 Appendix K I-ll N/A J-1.a-d 4.1.8, Appendix M J-2 Appendix N J-3 6.3, 9.3 J-4 6.3, 8.1.1, 9.3 J-5 8.1.4 J-6.a-c 6.6 J-7 8.2 J-8 , Appendix N P-5 ,a Q:J REVISION 3 MAY 21, 1982
, _ _ _ _ _ . .__.___~-_.~.__n_n_ 1
CPSES/EP J-9 N/A o J-10.a-b Appendix F J-10.c . 3.0 J-10.d-1 N/A J-10.m 8.2 J-11 N/A J-12 N/A K-1.a g 9.0 K-2 9.0, Appendix K K-3.a 6.3, 9.0 K-3.b 9.0, Appendix K K-4 , N/A K-5.a-b 9.0, Appendix K K-6 9.0, Appendix K K-7 9.0, Appendix K L-1 1.3.1.4, 10.0 L-2 1.2.1.13, 6.3 10.3 L-3 N/A L-4 1.3.1.3, 10.2 M-1 thru M-3 1.0 M-4 6.6 N-1.a-b 12.1 P-6 O REVISION 3 MAY 21, 1982
CPSES/EP N-2.a-e 12.2 ({}} N-3.a-f 12.0, 12.3 N-4, 5 12.0, 12.3 0-1,1.a 13.0 0-1.b N/A 0-2 13.0 0-3 thru 0-5 13.0 P-1 thru P-5 Preface, 14.0 P-6 15.0 P-7 Appendix K P-8 Page 1, Cross Index in Appendix P P-9 15.0 P-10 14.0, Appendix K P-7 Y) REVISION 3 MAY 21, 1982
~
CPSES/EP
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( .)
.s 'A APPENDIX Q Definitions and Acronyms Q-1 .)
REVISION 3 MAY 21, 1982
CPSES/EP AS BUILT DRAWINGS Drawings which provide the actual location, configuration or design of buildings, systems, and components throughout CPSES. CENTRAL ALARM STATION (C.A.S.) The principal monitoring and dispatching station of security activities for the Security Organization. CONTRACT PERSONNEL Any person or persons contracted directly by Texas Utilities l Generating Company to perform specific functions relating to the operation, maintenance, or refueling of the plant. These do not include personnel directly involved in construction of the plant. CONTROL ROGi A location within the plant from where all plant systems are operated and monitored. It is located on the 830' level of the Control Building. , DECONTAMINATION The transference of radioactive material (contamination) from an item or person where it is undesirable to a place where it is desirable (i.e. , wipe it off or wash it off). DEDICATED TELEPHONE Any telephone (instrument) so designated will have the same restrictions imposed as on a dedicated telephone line. DEDICATED TELEPHONE LINE Any telephone line, either within CPSES or outgoing from CPSES, that is designated for a specific use during an emergency. In the event this line is not in use, other uses of this line are prohibited until termination of the emergency situation and the plant is restored to normal operation. Q-2 O REVISION 3 MAY 21, 1982
CPSES/EP ] DEPARTMENT OF ENERG'f (D.O.E.) In the event of an emergency, the D.O.E. will furnish advice, consultation, and assistance regarding the protection of personnel, treatment of injured and/or exposed persons, minimization of further exposure and contamination, protection of materials, determination of existence and extent of decontamination, public and press relations and cleanup of radicactive materials. DOSE ISOPLETHS , A see-through overlay that when placed on an associated map will show projected doses at specific locations around CPSES. D.P.S. - THE TEXAS DEPARTMENT OF PUBLIC SAFETY The chief Agency, within the State of Texas, involved in disaster preparedness and offsite response during an accident at CPSES affecting areas outside the plant boundaries. DRILL A oupervised instruction period aimed at testing, developing, and maintaining skills in a particular operation. EMERGENCY ACTION LEVELS Specific radiation levels associated with airborne, waterborne, or surface-deposited concentrations of radioactive materials; or specific instrument indications (including their rates of change) that may be used as thresholds for initiating such specific emergency measures as designating a particular class of emergency, initiating a notification procedure, or initiating a particular protective action.
1. NOTIFICATION OF UNUSUAL EVENT Any abnormal condition, minor in nature, presenting no potential for the release of radioactive material, and requiring no offsite response or monitoring, is classed as an Unusual Event unless further degradation of safety systems occur.
Q-3
.s REVISION 3 MAY 21, 1982
CPSES/EP (N r.J
2. ALERT Events are in progress, or have occurred, which involve an actual or potentially substantial degradation of the level of safety of the plant. At the Alert action level, small release of radioactivity cay occur.

3. SITE ARE4 EMERGENCY Events which are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public, but a core meltdown is not indicated based on current information. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundaries. However, care must be taken in alerting offsite authorities to distinguish whether the release is merely potential, likely, or actually occurring.

4. GENERAL EMERGENCY Accident situations involving actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels for more than the immediate site area.
EMERGENCY COMMUNICATIONS PERSONNEL All persons involved with onsite and/or offsite communications at any time during an unusual situation in which emergency communications are established. EMERGENCY COORDINATOR , Designated onsite individual having the responsibility and authority for implementing the Emergency Response Plan and who will, when assigned the duty, direct all site efforts to Ibnit the consequences of the emergency and bring it under control. Q-4 O REVISION 3 MAY 21, 1982
CPSES/EP ['S
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EIC The Eberline Instrument Corporation. EliERGENCY OEPRATIONS FACILITY (E.O.F.) An area located near the site (.1.2 miles West of plant Security Building) with a usable physical facility that will be utilized to continually evaluate and coordinate activities related to an emergency having or potentially having environmental consequences. The facility will accommodcte representatives from Federal, State and Local governments, as appropriate. 10-li1LE E.P.Z. (EliERGENCY PLANNING ZONE) That area, approximately 10 miles in radius from the center of CPSES, for which emergency planning considerations of the plume exposure pathway have been given in order to assure that prompt and effective actions can be taken to protect the public and property in the event of an accident. t 50-MILE E.P.Z. (EMERGENCY PLANNING ZONE) That area, approximately 50 miles in radius from the center of CPSES, for which emergency planning considerations of the ingestion exposure pathway has been given in order to assure that effective actions can be taken to protect the public. EXPOSURE PROJECTIONS A calculated or expected exposure that would be received by population-at-risk individual (s) from direct radiation from a radioactive gaseous plume resulting from a radiological emergency if no protective actions are taken. l EXCLUSION AREA "That area surrounding the reactor, in which the reactor licensee has j the authority to determine all activities including exclusion or l removal of personnel and property from the area ...." (Ref. Code of Federal Regulations, Title 10, Part 100). Q-5 i l
,w l I ~
I REVISION 3 MAY 21, 1982
CPSES/EP b EXERCISE An event that tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and organiza tions. F.E.M. A. - FEDERAL EMERGENCY MANAGEMENT AGENCY This agency will provide guidance intended for use by State and Local goverusents that guide the emergency planning and preparedness activities. FEMA will make contributions when requested to assist in the development of State and Local plans. FSAR The Final Safety Analysis Report. N.R.C. - NUCLEAR REGULATORY COMMISSION The Federal Agency charged with the responsibility of insuring that Nuclear Power Plants are operated within Federal Guidelines and, should an abnormal situation occur, that all necessary actions are taken to regain control of the situation and prevent the situation from escalating to a larger problem. OFFSITE EMERGENCY OPERATIONS CENTERS Emergency centers established, outside of CPSES property boundaries, for the express purpose of assisting CPSES in the mitigation of an emergency situation. OWNER CONTROLLED AREA The area around the station that is owned by and, therefore, controlled by Texas Utilities. This area includes the exclusion area. P.I.G. MONITOR A particulate, Iodine and gaseous airborne radioactivity monitor. Q-6 h REVISION 3 MAY 21, 1982
CPSES/EP PLUME EXPOSURE PATHWAY PREDICTIONS Exposure predictions from a plume (radioactive cloud) are based principally on: A. Whole body external exposure to gamma radiation from the plume and from deposited materials, and B. Inhalation exposure from the passing radioactive plume. The time of exposure could range in length from hours to days. ' PROTECTIVE CLOTHING Special clothing (gloves, plastic or rubber shoe cov trs, coveralls, hoods, and respiratory protection devices) designed to prevent the wearer from becoming contaminated when entry into a contaminated area is required. RADIOLOGICAL MONITORING TEAMS Teams of technicians, fully qualified in all phases of radiological monitoring, that can be dispatched to conduct various types of surveys outside of the plant containment, in order to determine the actual magnitude of any release of radioactive materials. RMS COMPUTER The Digital Radiation Monitoring System Computer maintains a constant check on radiation levels, liquid concentrations, airborne concentration, and meteorologicel data during normal plant operations and emergency situations and can supply rapid assessments when needed. TECHNICAL SUPPORT CENTER (T.S.C.) A center outside of the Control Room that supplies technical information for use by technical and designated management personnel in support of plant operations and control during emergency conditions. It is located adjacent to the Control Room viewing area, on the 840' level of the Control Building. l Q-7
.i REVISION 3 MAY 21, 1982
CPSES/EP THYROID BLOCKING DRUGS A medication given to personnel who may be exposed to airborne radioactive iodine concentrations above the limits prescribed in 10CFR20, Appendix B, Table I, Column 1. SHIFT SUPERVISOR A member of management who holds a Senior Reactor Operator's license who is designated as being in charge of all Control Room functions. This individual is in the plant at all times. STATION ENVIRONS Any inhabitable area within the CPSES boundaries. SUPPORT ORGANIZATIONS Any organization or agency that is called upon to assist in the mitigation of an unusual situation. Q-8 h REVISION 3 MAY 21, 1982
CPSES/EP en
$cs APPENDIX R l
Westinghouse Electric Corp., Water Reactor Div. , Ectergency Response Plan i i l l l I i i R-1 REVISION 3 l W 21. 1982 1 .-
EMERGENCY RESPONSE PLAN WATER REACTORS DIVISIONS WESTINGHOUSE ELECTRIC CORPORATION i i 1 U Approved J. J. ylor V.P and General Manager Water Reactors Division Date: 6/1/80
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l l 2698A REVISION 3 l MAY 21, 1982
TABLE OF CONTENTS _ 1.0 PURPOSE AND SCOPE 2.0 ACTIVATION OF THE EMERGENCY RESPONSE PLAN 2.1 Introduction 2.2 Stages of an Event and Activation 2.3 Stage 1 - Initial Response 2.4 Stage 2 - Plan Activation 2.5 Stage 3-OperationofEmergencyRes6onseOrganizations 2.6 Stage 4 - Response by Functional Organizations 2.7 Deactivation of Emergency Response Organization 3.0 READINESS ASSURANCE 4.0 COMMERCIAL BASIS 5.0 APPENDICES
'.PPENDIX A - EMERGENCY RESPONSE COMMUNICATING NETWORK APPENDIX B - READINESS ASSURANCE PLAN PPENDIX C* - EMERGENCY NEWS COMMUNICATIONS CENTER (ENCC) PLAN - Table C-1 ENCC Roster APPENDIX D* - SERVICE RESPONSE PLAN - Table D-1 Early Response Team Roster
! - Table D-2 Site Response Team Roster APPENDIX E - TECHNICAL SUPPORT PLAN l APPENDIX F* - LOGISTICS AND ADMINISTRATION PLAN
*For internal Westinghouse use only.
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,. 3 REVISION 3 MAY 21, 1982
Westinghouse Water Reactors Divisions th Emergency Response Plan 1.0 PURPOSE AND SCOPE To define the Emergency Response Plan (ERP) for the Westinghouse Water Reactors Divisions (WRD) following an abnormal occurrence involving a nuclear power plant that releases or has the potential of releasing above normal amounts of radioactivity. This plan is primarily applica-ble to nuclear power plants located in the United States which have a I Westinghouse designed Nuclear Steam Supply System (NSSS), but may be activated for other cases contingent upon the ability of WRD to provide meaningful assistance and specific Westinghouse management approval. It is the intent of WRD to supply emergency assistance to our utility cus-tomers through this Emergency Response Plan (ERP) on a 24 hour / day, 7 day / week basis, i This plan is intended to define WRD operations as supoort to utilities emergency activities. Specifically this plan: i 1. , Defines the WRD emergency response organization, role, scope, func-l tions and responsibilitie:; and how it is activated.
2. Identifies the key WRD individuals to be available in the early phase of an emergency response.

3. Defines the prime WRD interfaces with involved parties.

4. Defines the WRD role in emergency news consnunications and the interrelationship with the utility site Emergency News Communica-tions Center and the news media.
Emergency Response Plan Director When activated the WRD Emergency Response plan becomes a functioning
,,, organization under the management of the plan Director. The ERP k,) Director is a senior WRD manager who during the time the plan is . 2698A REVISION 3 MAY 21, 1J82
_ . . . . ~ , .
activated has the same managerial authority as a division General
,., Msnager. The Director will report to the Vice President of WRD, the Vice President of NES, and other Westinghouse corporate management as appropriate, and will be responsible for similar high level interactions with the utilities senior manager responsible for Emergency Response and Recovery.
The ER Director's Staff consists of 5 individuals: Deputy Director: Responsible to manage the internal operation of the Plan. The Deputy makes the initial notifications to mobilize the operation of the plan and is responsible to maintain internal communication between the functioning parts of the plan. Emergency News Communications Manager: Responsible for external communications management as described in the Plan and in Appendix C, Emergency News Communication Center Plan. Service Response Manager: Responsible for mobilizing and directing plant and operational services as described in the Plan and in Appendix 0, Service Response Plan. , Technical Support Manager: Responsible for all technical advice provided to the Utility site and for mobilizing and managing the required technical resources as described in the Plan and in Appendix E, l Technical Support Plan. l Logistics and Administration Manager: Responsible for administration and f acilities and equipment needs as described in the Plan and in l Appendix F, Logistics and Administration Plan. 1 p ,,
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2698A j REVISION 3 l MAY 21, 1982 w . _ _ _ , , _ . . _ - - -
2.0 ACTIVATION OF THE EMERGENCY RESPONSE PLAN (h 2.1 Introduction This activation plan has been devised so that when the Director of the Emergency Response Team receives word of an abnormal occurrence in a Westinghouse-designed nuclear power plant, he takes certain actions that trigger decisions by himself and other responsible managers. These actions (A) and decisions (D) are shown as a series of alternatives in Figure A-1, which schematically describes how the fur.ctional organiza-tions set up in WRD will respond to a variety of situations. 2.2 Stages of an Event and Activation Any event is treated in a series of five stages from beginning to end
^
and all alternative actions are considered along with the decisions for response as may be required. The stages are as follows: Stage 1: This includes initial notification from any one of a number of sources, analysis of the problem, and the decision for the depth of response. l Stage 2: This covers the activation of all, part, or none of the response units within WRD. Stage 3: According to the magnitude of effort, the organizations in the Emergency Response Plan are made operational. Stage 4: During this period all activated functional organiza-tions are managed to ensure that all available l resources within WRD are applied toward informing the ! utility, the Nuclear Regulatory Comission (NRC), and the public. Stage 5: This step includes all actions taken which lead to deactivation of the plan. S l ') 2698A REVISION 3 MAY 21, 1982
2.3 Stage 1 - Initial Response O The first word regarding an incident may come from a number of sources in addition to the normally expected utility contact. Examples of potential reporting sources which might contact organizations within the Corporation such as an executive level, advocacy programs, a functional department, or a telephone operator are as follows: Nuclear Regulatory Commission
- News media (local news media, wire service etc.) -- State or local agencies - Federal Emergency Management Administration - Atomic Industrial Forum - An employee The actions and decisions described in paragraphs 2.3.1 and 2.3.2 cover any of these eventualities.
In any case, initial notification of an incident will trigger actions and decisions by either (or both) the Regional Service Manager (RSM) and the Emergency Response Plan Director (ERPD). Through all stages of an event WRD/NES Executive Management is consulted. The alternatives
. f acing the RSM and ERP Director uoon initial notification of an event are described in the following paragraphs.
2.3.1 Regional Service Manager The Regional Service Manager receives notification of an incident from the utility and he takes the following actions: l
a. Gathers available information about the incident.
l
b. Establishes a comunications interf ace with the ERP Director.
O u 2698A REVISION 3 MAY 21, 1982 . % _ _ __._ _ _ = ___ - _ - - _ _ . _ - . .-
c. Maintains the primary communications link with the utility until the
,s ERP director has the WRD response organization in place.
kI) The Regional Service Manager has the following choice of decisions:
a. Based on available-information, he judges that the ERP should be activated. He calls the ERP Director and makes his recommendation.

b. If activation in his opinion is questionable, he may call appropri-ate NSD managers to arrive at a joint decision. Cognizant NSD mana-gers may then call the ERP Director, to request activation.

c. Either singly, or in joint consultation with NSD managers, is decided that only functional organizations need be activated for response to the utility problem then the ERP is not activated.
2.3.2 Emergency Response Plan Director
a. Inform Vice President WRD of incident and action he recommends.

b. Inform the Regional Service Manager of which action is to be taken.
When notified of an incident, the ERP Director has the following deci-sions to make:
a. He may pass on the response directly to the responsible functional organization within WRD (NSD, NTD, NFD, etc) without activating the Emergency Response Plan.

b. In consultation with the VPs WRD/NES he decides to activate the ERP and advises his Deputy Director to do so.

c. He may return the responsibility of a response to the Regional Ser-vice Manager.

d. Inform the Regional Service Manager of which action is to be taken.
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'm) 2698A REVISION 3 MAY 21, 1982
- . . .. - . . . . ~ .-. -
2.3.3 Special Cases ' h If an event takes place at a non-Westinghouse nuclear steam supply system, the WRD Emergency Response Plan may be activated by the ERP Director with the appropriate approvals. Requests for assistance and the manner of handling it are funneled through the ERP Director. In addition, a legal / commercial basis must be established to define the terms of assistance. If an event occurs in an overseas Westinghouse Nuclear Steam Supply System, the WRD Emergency Response Plan may be activated with corporate approvals to support the in-country agreements set up by WNI/PSPD. In this case, primary interf aces will be established on a country-by country basis. 2.4 Stage 2 - Plan Activation At this point, the decision for total or partial activation has been made. The (A)ction, (D)ecision phase involves only the Director of the Emergency Response Plan. In Stage 2 the ERP Director acts as follows:
a. He activates the Emergency News Comunication Center (ENCC), whose director has the discretion to forward information as he deems nec-essary, with approvals of higher management and af ter appropriate consultation with the affected utility news communicator.

b. He activates only the WRD Comunications Network, a skeleton organi-zation of key communications and technical personnel who maintain lines of information among WRD, NRC, the pertinent utility, and the public.
l
c. He activate's the entire Emergency Response Plan. In addition to the ENCC, he will activate the appropriate service response organiza-I tions, the Technical Support Team (in MNC 418A/415D), the Command Center (in MNC 501/502C), and the Logistics and Administration Sup l .,
l ') I 2698A REVI$ ION 3 MAY 21, 1982
port functions. Having established contact with RSM, as described in Stage 1, he will advise the RSM to maintain site contact with the () utility until ERP members have arrived at their assembly points in the fluclear Center , at which time they will be ready to respond to the situation. The Site Response Team (three specialists and an appropriate RSM) with the approval of the utility will have been dispatched to the site to participate as needed in the recovery operation and feed back information to the ERP Director. 2.5 Stage 3 - Operation of Response Organizations There are three key persons involved during this stage of an incident. They are the Service Response Manager, the Technical Support Manager, and the Logistics and Administration Manager. The actions and decisions they must make are described in the following paragraphs. 2.5.1 Service Response Manager The Service Response Manager has the primary responsibility for directing all service activities in coordination with the Emergency Response Plan Director. Based on the severity (urgency) and definition i of the incident and the need for on-site presence of specialists from within WRD, he is faced with the following decisions to be made:
a. Activate the Site Response Team imediately and dispatch them to the l
site by the f astest means available, enlis, ting the aid of the Logis-tics and Administration Manager if necessaey.
b. Place the Site Response Team on a standby basis with the SRT leader moving to the MNC Comand Center.

c. Contact the app'ropriate functional (service) organization and advise l it to respond as appropriate.
f) 2698A REVISION 3 MAY 21, 1982
.....~. ~ ~ -.-.. ~ . .. . - = - -
2.5.2 Technical Support Manager ('y
/
The Technical Support M&'ager is responsible for technical advice relayed to the customer and for obtaining the approval of higher manage-ment as he judges necessary. He has one of the following decisions to make:
a. Fully activate the Emergency Technical Center (MNC 418/415) and assemble all members. He then serves as the group's interface with the Command Center and other functional groups, requesting whatever '
additional support is needed.
b. Partially activate the Emergency Technical Center to include members fully conversant only with those areas of immediate concern. The remaining members of the ETC are placed on standby.

c. Do not activate the Emergency Technical Center, but request support directly from the appropriate functional group.
2.5.3 Logistics and Administration Manager The Logistics and Administration Manager will have the primary responsi- ' bility for supplying material, f acilities, transportation, and communi-
. cations links based upon the decisions and actions of other ERP members . These responsibilities may include any or all of the following:
a. Update security force on anticipated arrival / departure of news media personnel, based on depth of operation of ENCC.

b. Arrange transportation, equipment transfers, purchases, cash advances, etc., to support service response activities.

c. Rearrange furniture or other equipnent within WRD facilities in support to ERP team needs, t
4 v r 2698A REVISION 3 MAY 21, 1982
d. Establish special communications links (telephones, wire services, intercoms, etc.) as dictated by the situation.
(9
e. Provide for movement of information from the Information Resources Center or Records Center as needed.

f. Supply additional graphics / audio visual / video support needed by ERP operations,

g. Call for a standby situation for various support services as de~ scribed in Section 2.3.2a.

h. Relinquish responsibilities to functional organizations.
2.6 Stage 4 - Response by Functional Organizations During this stage the recovery process is under way. The ERP Director and the ERP staff manage all of the organizations that have been acti-vated to assist the utilities in its efforts to control and recover from the incident. Responsibility is transferred in an orderly fashion to expedite the work of functional organizations or appropriate special project or task forces that may have been established. 2.7 Stage 5 - Deactivation of Emergency Response Organization This is the final stage and formal end of the Emergency Response Plan. Responsibility is moved out of the ERP framework at such time as the ERP Oirector is satisfied that the emergency is terminated and the ERP is no longer needed. The ERP Director will then formally advise all involved i.e. utility, NRC, and the Westinghouse organization involved, that the plan has been deactivated. 4 2698A REVISION 3 MAY 21, 1982 m _ _ ..._. ...~ . _ _ , _ . - . _ _ _ _.-m - - _ - . . _ , _
.- . . . . .....-~-. ..
3.0 READINESS ASSURANCE (9) 3.1 Audits /0 rills Annually the Emergency Response Plan Director will arrange for a con-plete operational evaluation of this plan. This will include a sample audit of the Emergency Technical Center Reference Library, phone commu-nications network and may include drills. WR0 will also participate, as requested, in utility initiated drills. These audits and drills will be documented for review by Westinghouse corporate management. 3.2 Training The Emergency Response Plan Director will also hold annual familiariza-tion sessions and establish specific training based on feedback from these sessions, l I b l 2698A l l REVISION 3 l MAY 21, 1982
i. _ - .
4.0 COMMERCIAL BASIS ~ t.-i Westinghouse will furnish Emergency Assistance Services 'as specifically described in the " Westinghouse Emergancy Response Plan," to the utility requesting such services (hereinafter " User"). The emergency assistance period begins at the time of initial notification by the User to Westinghouse of an abnonnal occurrence involving its nuclear power plant that releases or has the potential of releasing above normal amounts of radioactivity and shall terminate when the Westinghouse Emergency Response Organization and the Emergency Response Plan is deactivated. Compensation Westinghouse will perform the Emergency Assistance Services stated here-in at no cost to the utility during the first three (3) days of such emergency. The remaining period of performance of such services shall be performed on a firm price basis, with or without price adjustment, and/or on a time and material basis, said basis to be agreed upon prior to the expiration of said three (3) day period. The remaining terms and conditions during activation of any part of the Westinghouse Emergency Response plan will be provided in a separate document. l l l (
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2698A REVISION 3 MAY 21, 1982 l
.w n .- - -- = -m w ~ ~
APPENDIX A { ERP COMMUNICATIONS PLAN If an event at a Westinghouse designed NSSS occurs that might require full scale Westinghouse Emergency response, the plant operator should:
1. Immediately contact the Westinghouse Regional Service Manager (RSM).
Two numbers are provided, the "off hours" (home) number listed is a special dedicated line which is equipped with an answering device which when the RSM is not available, will give the caller instructions, take a message and when the caller hangs up, will automatically begin calling both of the RSM alternates until it gets an answer and an acknowledgment tone.
2. If in a reasonable period no response is received the Reactor Plant Operator should contact the Service Response Manager.
This will initiate the actions described in the plan and shown in Figure A-1. Upon full activation, comunication links and advisories will be estab-lished as shown on Figure A-2. The primary link will be between tha site and the RSM until the plan is fully activated. At this time the prime link is betwen the ERP Director and the Utility Recovery Manager. Support links will be established with the Site Response Team upon their arrival on site, the Onsite Technical Support Center and the Site Emergency News Communications Center. Advisory communications will be made, as appropriate with the U.S. NRC, (RRG), Institute for Nuclear Power Operating Regulatory Response, NSA, other Westinghouse plants, l Architect /Egnineers, etc. n b) A.1 l 2698A l REVISION 3 MAY 21, 1982. + ~ . . - , - . . _- - _ - _ - - , n,n_
FIGURE A-1
,, ERP COMMUNICATION PLAN - ACTIVATION Q
UTILITY PLANT OPERATOR v v v W WRD REGIONAL SERV. <-+ ALT #1 < > ALT #2 MANAGER v v v __ W WRD ERP < > ALT #1 < > ALT #2 ' DIRECTOR
+
W EXECUTIVE ADVISORY v v v W WRD DEPUTY : > ALT #1 < > ALT #2 DIRECTOR U Y Y I t SERVICE TECHNICAL LOGISTICS & EMERGENCY RESPONSE SUPPORT ADMINISTRATION I NEWS COMM. MANGER MANAGER MANAGER I MANAGER l l - ALT 1 + - - - + -ALT 1 ALT 1 + b - + ALT 1
- ALT 2 4 - - - + - ALT 2 ALT 2 4 - + ALT 2 t
l
,n M~
2698A l REVISION 3 MAY 21, 1982
FIGURE A-2 as ERP COMMUNICATION PLAN - ADVISORY IJ WR0 UTILITY OPERATOR ERP : REC 0VERY MANAGER t l SERVICE WESTINGHOUSE
: SITE RESPONSE l MANAGER RESPONSE TEAM TECHNICAL UTILTY ON-SITE SUPPORT TECHNICAL SUPPORT -
MANAGER CENTER NUCLEAR ETC.
--* REGULATORY COMMISSION
INPO IRRG INSAC ETC.
EE R. NEWS UTILITY OPERATORS COMMUNICAT. : EMERGENCY NEWS MANAGER COMMUNICATIONS DIRECTOR NEWS _ EDIA WRD NSSS OTHER OPERATING & NON OPERATING PROJECT WESTINGHOUSE - MANAGER PLANTS /ETC. AIE'S
. --* CONSTRUCTORS -
ETC. (f"S 2698A REVISION 3 MAY 21, 1982
APPENDIX B READINESS ASSURANCE PLAN (};}; In order to assure readiness WRD will Drill / Audit and train as outlined in Section 3 of the plan. The Deputy Director will be responsible for these actions. Training: At least once a year the Deputy Director will hold a plan f amiliarization session where all major facets of the plan will be reviewed. The tratning will include: a) Review of procedures b) Review of f acilities c) Review of responsibilities of contact personnel The general outline of the review and those participating will be docu-mented and made available for Westinghouse Corporate Audit. Drills: A Drill Master will be assigned by the Deputy Director to ensure that at least one unannounced drill is held during each 12 month period. This drill may be initiated in co-operation with a utility initiated drill or by the Westinghouse ERP Drill Master. In all cases each drill instruction will begin with the words "This is a Drill, repeat drill of the WRD Emergency Response Plan" before providing instructions. From time to time comunications network drills will be held to assure minimum team manning capability. The Westinghouse ERP Drill Master will be responsible for maintaining records of these drills for Westinghouse Corporate Audit. Audits: Audits on ,an annual basis will be made by a Westinghouse cor-parate Audit group to assure readiness and accuracy and completeness of response plans training and reference materials. The results of these audits can be made available to operating utilities on written request. h 2698A B.1 REVISION 3 MAY 21, 1982
l l APPENDfX E I (} TECHNICAL SUPPORT PLAN Functions The Emergency Technical Center (ETC) functions as a part of the WRD i Emergency Response Plan. l l The ETC provides the key communications link with the utility Technical Support Center (TSC) through which pertinent plant data and system con-ditions are received by Westinghouse. The Emergency Technical Center shall provide dedicated and timely assis-tance to utilities in the early stages of an emergency involving release or potential release of above nonnal amounts of radioactivity. This assistance will derive from an established technical capability or understanding which the utility may not readily possess or for which the utility desires additional or corroborating effort. Assistance can consist of analysis support, technical evaluations, advice, or any other form appropriate to the emergency at hand. This technical support and data comunications shall be provided to the utility and other organizations of the WRD Emergency Response Plan via the Early Response Team (ERT) in the Emergency Response Comand Center. Activation l Activation is by dec'ision of the Early Response Team through the ETC Manager or designated alternate. Activation shall be affected on a case-by-case basis as soon as it has been determined that data acquisition and plant technical support is desired. h 2698A E.1 REVISION 3 MAY 21, 1982
. ~ - _ n , n _ -_ __ _ - _=_ n _ = n _ - _, n n _ . _ __
Once authorized, activation and organization of the ETC function shall proceed in parallel with assembly of the ERT under the authority of the ETC Director, who is designated by the Technical Center Manager. RESPONSIBILITIES Technical Center Manager The Technical Center Manager is responsible for assuring that necessary equipment and resources within the ETC are complete and in operating order. The Technical Center Manager will assure that an adequate roster of key personnel is provided to the ETC Director and is continually updated to support ETC staffing requirements. The Technical Center Manager is responsible for providing the ERT with timely plant data as received from the utility technical support center or other sources via the ETC communications links. The Technical Center Manager is responsible for all technical support and recommendations provided for the use of the utility, NRC or other organizations by the ETC staff. The Technical Center Manager will serve as the single Westinghouse spokesman for technical support. The Technical Center Manager is responsible for informing the appropri-ate Nuclear Safety line organization of the existence and nature of the emergency and to authorize Nuclear Safety line organization effort or involvement as appropriate to the situation at hand. The intent is to anticipate and effect the eventual transition to normal line management responsibility. The Technical Center Manager is responsible for assuring that appropri-ate records are maintained for ETC operations. (h 2698A E.2 REVISION 3 MAY 21, 1982
The Technical Center Manager will judge then the state of emergency is ever and recomend to the Emergency Response Director that the ETC be deactisated. Upon approval of the Emergency Response Director, he will:
1. Assign continued line management responsibilities as appropriate, and

2. Direct the preparation of an event report describing the nature and progress of the emergency including:

a. A chronological sequence of key events

b. A description and sumary of ETC efforts and results

c. A critique of the event itself and the ETC operations with appropriate recomendations.
ETC Director: The ETC Director is responsible for initial ETC staffing and maintaining an effective staffing level throughout the emergency. The ETC Director is responsible for all ETC data communications, recom-mendations, and technical support provided to the ETC Manager. The ETC Director will serve as the single ETC spokesman for communica-tions with the WRD Emergency Response Comand Center. The ETC Director is responsible for overall direction of ETC technical activities associated with each particular emergency, including documen-tation of ETC efforts. The ETC Director is responsible for serving as communication link to obtain plant / event data from NRC when directed by the Technical Center Manager, h 2698A E.3 REVISION 3 MAY 21, 1982
STAFFING ([] Initial staffing of the ETC will be by selection from a roster of key personnel maintained by the Technical Center Manager at all times. Candidates for appointment as ETC Director, depending on the particular emergency, shall be identified on the ETC Staffing roster. The Techni-cal Center Manager and his designated alternate, the Emergency Response Director and his designated alternate and all key personnel on the ETC staffing roster will possess copies of this roster at all times. The roster will be on continuous and conspicuous display in the ETC while actuated. The ETC Director, once appointed, will effect the initial staffing of the ETC by appropriate selection from this roster. The requirements for this roster are as follows:
1. A minimum of five individuals shall be identified by name from each of the following second level groups:

a. Licensing and Safety Evaluation

b. Reactor Protection

c. Safeguards Engineering d, Fluid Systems Design

e. Systems Analysis and Operations

2. Each individual shall be identified by:

a. Name

b. Group 2698A E.4 REVISION 3 MAY 21, 1982

c. Area (s) of technical expertise h d. Plants or groups of plants for which the individual may have special f amiliarity

e. Work extensions and home telephone numbers

f. Any other special characteristics which may be relevant.

3. Individuals shall be selected such that, collectively and is a minimum, technical capability exists in the folicwin; areas:

a. Safeguards Systems l b. B0P Systems Design

c. Functional Analysis

d. Nuclear Operations

e. Reactor Protection Analysis

f. Safeguards Analysis

g. Mechanical and Fluid Systems Evaluation

h. Emergency / Abnormal Operating Procedures

1. Environmental and Operational Safety

4. The names and telephone numbers of the managers of the following groups shall also be provided on the roster sheet:

a. Manager, Steam Generator Systems & Materials

b. Manager, Plant Systems dh w 2698A E.F REVISION 3 MAY 21, 1982
- - ~..__ _-. .- _ _ _ . , _ . - _ -
c. Manager, Fluid Systems Design -

d. Manager, Electrical Systems Application b,,

e. Manager, Applied Mechanics Department

f. Manager, Systems Analysis and Operations

g. Manager, Licensing and Safety Evaluation

h. Manager, Safeguards Engineering

i. Manager, Reactor Protection

j. Manager, Nuclear Engineering

k. Manager, Fuel Performance Engineering and Evaluation OPERATIONS The Technical Center Manager shall assume all responsibilities of the ETC and the ETC Director until such time as the ETC Director has estab-lished functional operation of the ETC.
The Technical Center Manager shall report directly to the Command Center (MNC 501) from where all technical support to the utility will be authorized. l The designated ETC Director shall report'directly to the ETC (MNC, CR 418) and assure establishment of the following:
1. Initial staffing level

2. Com.unications link with Technical Center Manager in the Comand Center Q 2698A l E.s REVISION 3 l MAY 21, 1982 ,
l
3. Utility-!!cstinghcuse data communications link The ETC Director shall establish initial staffing of the ETC consistent with the staffing criteria outlined above, and designate individual responsibilities to the ETC staff for, at minimum, the following func-tions:

1. Site Communications Function Responsible for continued ongoing interface with site Technical Support Center.
Obtains plant status as of ten as warranted, and fills out Plant Event Data Sheet. I Obtains basic information on event, site evaluation of probable event prognosis, and site recovery plans. Along with ETC Director, is only external interf ace from ETC.
2. Emergency Procedure Function Establishes likely post-accident operator actions based on pl ant specific procedures.
Compares plant-specific procedures with applicable Westinghouse l reference 'nstruction. Identifies likely future course of action based on plant i procedures I Evaluates applicability of Westinghouse Reference E0!"s l for future reference and recomendations. Evaluates plant transient against the analytica vesis for Westinghouse / Utility emergency guidelines. Q 2698A E.7
' REVISION 3 MAY 21, 1982 l
_ _ _ _ _ _ a
3. Data and Facility Management
- Responsible for Plant Event Data Board updates and maintenance.
(]
- Continual log of ETC activity including chronological data sheets.
Reports to ETC Director for duties related to ETC staffing, f acility organization and in-house plant data availability. Establishment of ETC hardware required for emergency tele-comunications with the site and the ETC communications system with the Emergency Command Center and the ENCC.
4. Event Analysis / Evaluation Responsible for evalu: tion of site data as to data consistency and sufficiency for event evaluation.
- Provide event evaluation as to recovery alternatives, concerns and event diagnosis verification. - Provide radiological evaluation for past and potential future releases.
Initial Operation of the ETC consistent with the functional responsi-bilities identified above is expected to consist of one manager, five to seven engineers and one engineering aide. Access to the ETC areas shall be restricted to those identified by either the Technical Center Manager of the designated Technical Center Director of Operations. A functional diagram depicting ETC organization structure is provided in Figure 1. am h) 2698A E.8 REVISION 3 MAY 21, 1982
Comunications requirements for effective ETC operation may be categor-() ized as follows: Plant Site Data Comunications In the near term, prior to realization of advanced plant site Technical Support Centers, the primary comunication mechanism for plant data and status will be via a two-way speaker phone. This line should also be- connected as a reception - only intercom in the Comand Center. A redundant headphone with sound actuated microphone equipped with a long extension cord connected to the same line as the speaker phone should also be provided in the ETC. This would permit mobi-lity by the site ecmunications engineer when required, without disruption of other ETC activities.
- A telecopy machine for printed material should be imediately available to the individual performing the data management func-tion. The teleccoier f acilities in the Word Processing Center on the fourth floor, MNC, should serve this purpose. - A tape recorder to be used for infonnation verification of plant conditions obtained from the speaker phone link is necessary.
Operation of this recorder is under the authority and responsibil-ity of the ETC Director. Comand Center Comunications Closed circuit T.V. feed of the Plant Event Data Board should be continuously, provided to a monitor in the Comand Center and avail-able for viewing on the monitors alrea1y located in the ENCC (MNC, Auditorium) . h 2698A E.9 REVISION 3 MAY 21, 1982
- A headphone equipped with sound actuated microphone should be pro-([)) vided as a direct link from the ETC Directer to the Technical Center Manager 1ccated in MNC 501. The capability should exist for this line to also operate as a nohnal speakerphone. - An additional speakerphone should be available in C.R. 415 for ETC use to other internal and external resource centers. - In order to f acilitate receiving infennation frem NRC then author-ited, the capability fer applying a separate phone line as a three-way hookup with the ETC Directer and the Technical Center Manager should exist.
.I e l i. 2598A E.10 REVISION 3 MAY 21, 1982
~
Attachment 2 Northern Service Region Emercency Cc=unication Network Title Name Office Home *HHL
1. Regional Service Manager Bob Kelly 1st Alternate Tem Dent 2nd Alternate Bob Grimm

2. Service Response Manager Joe Leblang 1st Alternate Bob Stokes 2nd Alternate LeeCunninghaml

3. Emergency Response Director Hank Ruppol

4. Emergency Response Deputy Ron Lehr Director ,
5 ." Emergency News
Mike Mangan s Communications _-
- ~
Please infor n one Westinghouse contact, using this list in the order shown, to ensure early notification to E of an emergency occurring at your plant. Please be prepared to discuss as many facts as are available at the time of the call and identify a cog-nizant individual in your organization to provide continuing communications and update: to E.
*Home Hot Line (HHL). These phones are to be used only during "off" hours. Any emergencies occurring during regular office hours are to be channeled through the office phones. The emergency (HHL) phones answer 24 hours / day and are especially designated as emergency numbers. They are equipped with automatic call forwarding features in the event that no one answers. The system works in the following manner:
The phone will answer requesting you to state your name (please provide the spelling if there is room for confusion), your phone number, and the nature of the problem. 31 ease note that you must stay on the line for a minimum of fifteen (15) seconds to initiate the call fonrarding. After you finish your message and hang up, the phone will then ring two (2) pre-programed numbers, each every four (4) minutes until a phone is answered and the message given. If after leaving a message with a call for-warding device, no one'has contacted you within ten (10) minutesi call the second name on the list, and, if necessary, repeat the process. Note: Unless indicated otherwise, all phone numbers are area code 412. Where an area code other than 412 is shown, it applies to the office, hcme, and NHL numbers.
. =.: M * ~
(9 . : . REVISION 3 MAY 21, 1982
t
'Q Attachment 2 - Southern Service Reofon .Emercency Comunication Network
Title Name Office g *HHL

1. Regional Service Manager Steve Longdon I ,

2. 1st Alternate John Willis '

3. 2nd Alternate Dave Richards

4. Service Response Manager Joe Leblang ist Alternate Bob Stokes ,
i 2nd Alternate Lee Cunningham l S. Emergency Response Director Hank Ruppel
6. Emergency Response Deputy Ron Lehr Director ;

7. Emergency News Mike Mangan Comunications -
_ ~ . . . . - Please inform one Westinghouse contact, using this list in the order shown, to ensure , early notification to W of an emergency occurring at your plant. Please be prnpared to discuss as many facts as are available at the time of the call and. identify .. cog-nizant individual in your organization to provide continuing comunications and update. I to W.
*Home Hot Line (HHL). These phones are to be used only during "off" hours. Any
, emergencies occurring during regular office hours are to be channeled through the
office phones. The emergency (HHL) phones answer 24 hours / day and are especially designated as emergency numbers. Thay are equipped with automatic call forwarding features in the event that no one answers. The system works in the following manner:
The phone will answer requesting you to state your name (please provide the spelling if there is room for confusion), your phone number, and the nature of the problem. Please note that you must stay on the line for a minimum of fifteen (15) seconds to initiate the call forwarding. After you finish your message and. hang up, the phone will then ring two (2) pre-programed numbers, each every four (4) minutes until a phone is answered and the message given. If after leaving a message with a call for-warding device, no one has contacted you within ten (10) minutes, call the second name on the list, and, if necessary, repeat the process. Note: Unless indicated otherwise, all phone numbers are area code 412. Where an y . area code.other than 412 is shown, it applies to the office, home, and HHL:. (,y - numbers. T i REVISION 3 MAY.21, 1982
Attachment 2 O d Eastern Service Reofon Emercency Communication Network , Title Name Office Home *HHL
1. Regicnal Service Manager Frank Noon 1st Alternate Ray Sabol 2nd Alternate .
Dallas Lokay Service Response Manager Joe Leblang ist Alternate Bob Stokes (Al t) 2nd Altarnate Lee Cunningham (Alt)
3. Emergency Respense Director Hank Ruppel '

4. Emergency Response Deputy Ron Lehr Ofrector

5. Emergency News Mike Mangan Ccmmunications ._ _,___
Please inform one Westinghouse contact, using this list in the order shcwn, to ensure early notification to W of an emergency occurring at your plant. Please be prepared to discuss as many facts as are available at the time of the call and identify a cog-
~
nizant individual in your organization to provide continuing communications and updates to W.
*Home Hot Line (HHL). These phones are to be used only during "off" hours. Any emergencies occurring during regular office hours are to be channeled through the office phones. The emergency (HHL) phones answer 24 hours / day and are especially designated as emergency numbers. They are equipped with autcmatic call forwarding features in the event that no one answers. The system works in the following manner:
The phone will answer requesting you to state your name (please provide the spelling f there is rocm for confusion), your phone number, and the nature of the problem.
. lease note that you must stay on the line for a minimum of fifteen (15) seconds to initiate the call forwarding. After you finish your message and hang up, the phone will then ring two (2) . pre-programmed numbers, each every four (4) minutes until a phone is answered and the message given. If after leaving a message with a call for-warding device, no one has contacted you within ten (10) minutes, call the second name 9 the list, and, if necessary, repeat the process.
Note: Unless indicated otherwise, all phone numbers are area code 412. Where an area code other than 412 is shown, it applies to the office, home, and HHL numbers. _ _g h REVISION 3 MAY 21, 1982 <
o-V), Attachment 2 Western Service Recion Emercency Communication Network Title Name Office Hcme *HHL
1. Regional Service Manager Lee Cunningham lst Alternate (Alt' Cliff Lissenden 2nd Alternate Pat Docherty

2. Service Response Manager Joe Leblang ist Alternate Bob Stokes 2nd Alternate (Alt)
Lee Cunningham
3. Emergency Response Ofrector Hank Ruppel

4. Emergency Response Depu ..- Ron Lehr Ofrector

5. Emergency News Mike Mangan Communications Please inform one Westinghouse contact, using this list in the order shown, to ensure early notification to E of an emergency occurring at your plant. Please be prepared to discuss as many facts as are available at the time of the call and identify a cog-nizant individual in your organization to provide continuing communications, and updates to 1
*Home Hot Line (HHL). These phones are to be used only during "off" hours. Any emergencies occurring during regular office hours are to be channeled through the office phones. The emergency (HHL) phones answer 24 hours / day and are especially designated as emergency numbers. They are equipped with automatic call forwarding features in the event that no one answers. 'The system works in the following manner: 'he phone will answer requesting you to state your name (please provide the spelling . .f there is room for confusion), your phone number, and the nature of the problem.
Please note that you must stay on the line for a minimum of fifteen (15) seconds to initiate the call forwarding. After you finish your message and hang up, the phone will then ring two (2) p're-progran:ed numbers, each every four (4) minutes until a phone is answered and the message given. If after leaving a message with a call for-arding device, no one has contacted you within ten (10) minutes, call the second name n the list, and, if necessary, repeat the process. Note: Unless indicated otherwise, all phone numbers are area code 412. Where an area code other than 412 is shown, it applies to the office, home, and HHL_ numbers. S (d REVISION 3 MAY 21, 1982
Attachment 3 e-ki) Technical Center Library I. PLANT LAYCUT DRAMINGS A. Plot Plan B. Nuclear Tank Farm General Arrangement C. Primary Aux. Bldg. Arrangements D. Aux. Feed Pump Bldg. Arrangements E. Waste Holdup Tank Pit Arrangement F. Fuel Storage Bldg. Arrangement G. Turb,ine Bldg. Heater Bay Arrangements H. Containment Bldg. Arrangements II. SYSTEMS DCSCRIPTIONS A. RCS B. Auxiliary Coolant System C. CVCS D. Waste Disposal System E. ESF F. Main and Reheat Steam G. Feedwater, Extraction Steam and Heater Drain Systems H. Service Water and Cooling Water III. FLOW DIAGRAMS A. RCS B. CVCS C. SIS REVISION 3 MAY 21, 1982
Attachment 3 (Cont'd) C- Technical Center Library D. ACS E. Waste Disposal System F. Nuclear Equipment Drains G. Sampling System H. Main Steam I. Condensate and Boiler Feed Pump Suction J. Cond. and Boiler Feed Pump Suction Electrical Freeze stection K. Boil,er Feedwater L. Service and Cooling Water River Water and Fresh elater M. Service Water System IV. FUNCTIONAL LOGIC DIAGRAMS A. Reactor Trip Signals B. Turbine Trip Signals C. 6900 v. Bus Auto Transfer D. Nuclear Instrumentation Trip Signals E. Nuclear Instrumentation Permissives and Blocks F. Emergency Generator Starting G. Safeguards Sequence H. Pressurizer. Trip Signals I. Steam Generator Trip Signals J. Reactor Coolant System Trip Signals and Manual Trip K. Safeguards Actuation Signals , L. Feedwater Isolation () REVISION 3 MAY 21, 1982
--- . _ . . _ - ~ _ _ ~ - . _ _ _ - . - - _
Attachment 3 (Cont'd) () , Technical Center Library M. Rod Stops and Turbine Load Cutback N. Setpoints for Reactor Control and Protection Systems V. SINGLE LINE DIAGRAMS A. 480 Volt Motor Control Centers and Instrument Buses B. 0.C. System i VI. INTERLOCK SHEETS A. RCS B. Auxiliary. Coolant System C. CVCS D. Waste Disposal Systems E. ESF VII. ALARM & CONTROL SETPOINTS A. RCS 1 B. Auxiliary Coolant System C. CVCS 1 D. Waste Disposal System E. ESF l l VIII. COOLANT ACTIVITY DATA l ,, IX. STEAM GENERATOR OPERATING HISTORY ( ,1 REVISION 3 MAY 21, 1982 l
~ . - . - _ _ . _
Attachment 3 (Cont'd) Technical Center Library X. INDEX OF READ 00TS, ALARMS, AND CONTROL S!41TCHES ON MAIN CONTROL BOARDS A. RCS B. Auxiliary Coolant System C. CVCS D. Waste Disposal System l E. ESF F. Main Steam G. Main,Feedwater H. Auxiliary Feedwater I. Service Water i 1 Ci REVISION 3
~
MAY 21, 1982
Mr. D. V. Shaller, Plant Manager Mr. S. S. Zulla, Superintendent of Pcwer
0. C. Cook fluclear Plant Power Authority of the State of tiew York (3
; Indiana and Michigan Power Company P. O. Box 215 P. O. Box 458 Buchanan, ?!ew York 10511 Bridgman, fitchigan 49106 Jcc: R. W. Jurgensen jcc: J. P. Bayne J. E. Dwyer W P. J. Early K. S. Sunder Raj P. W. Lyon Mr. R. H. Graves, Plant Superintendent W. A. Josiger Haddam tjeck Plant G. J. Keane Connecticut Yankee Atomic Power Company J. M. Clabby RR#1, Box 127E E. V..Somers East Hampton, Connecticut 06424 W. G. Cheney W Jcc: J. M. Kufel R. P. Traggio Mr. F. P. Librizzi, General Manager R. F. Wille W Electric Production Public Service Electric and Gas Company 80, Park Place Mr. J. A. Herling.. Plant Superintendent Newark, New Jersey 07101 Beaver Valley Power Station jcc: H. J. Midura Duquesne Light Company H. J. Heller hi i gport, Pennsylvania 15077 f,' r jcc: G. W. Moore R. A. Uderitz h, f' h , n3 E.' N hwalje J. J. Carey T. N. Taylor J. D. Sieber D. J. Jagt F. W. Knowles W C. F. Barclay -W Mr. B. A. Snow, Plant Superintendent Mr. W. A. Monti, Manager Ginna Nuclear Station Nuclear Power Generation Rochester Gas and Electric Corporation Consolidated Edison Company of New York, Inc. 1503 Lake Road Broadway and Bleakley Ontario, New York 14519 Buchanan, New York 10511 l jcc: J. C. Noon l Jcc: M. F. Shatkouski L. D. White l J. Curry L. S. Lang l A. A. Nespoli . J. E. Arthur J. M. Makepeace R. E. Smith A. V. Jaffe J. C. Hutton G. J. Keane R. C. Mecredy E. R. McGrath C. R. Anderson P. Zarakas A. E. Curtis W. J. Cahill J. L. Carlson W M. L. Lee E. V. Somers 9,
W. G. Cheney W REVISION 3 l MAY 21, 1982
Mr. H. A. Autio, Plant Superintendent Yankee Atomic Electric Company Rowe, Massachusetts 01367 {} Jcc: N. N. St. Laurent D. E. Moody P. T. Conroy W Mr. R. L. Sullivan, Project Administrative Engineer Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 jcc: P. Yundt S. R. Christensen Mr. H. O. Thrash, Manager J. W. Lentsch Nuclear Generation Alabama Power Company C. Goodwin 600 North Eighteenth Street J. W. Martindell H Birmingham, Alabama 35291 e jcc: J. T. Young Mr. J. M. Curran, Plant Manager " "' t San Onofre Nuclear Generating Station Unit 1 P. O. Box 128 M. C. Brickell W. G. Hairston, III San Clemente, California 92672 R. W. Wise W - Jcc: H. L. Ottoson J. G. Haynes K. P. Baskin Mr. B. J. Furr, Vice President D. K. Nelson Nuclear Operations J. L. DeHass W- Carolina Power & Light Ccmpany P. O. Box 1551 Raleigh, North Carolina 27602 jec: R. M. Coats R. B. Starkey E. G. Hollowell B. H. Webster J. F. Halifax W Mr. C. O. Woody, Manager Power Resources, Nuclear Florida Pcwer & Light Company P. O. Box 529100 Miami, Florida 33152 Jcc: A. D. Schmidt W. H. Rogers, Jr. H. E. Yaeger t J. K. Hays () E. V. Rutledge W REVISION 3 MAY 21, 198
em Mr. B. R. Sylvia, Manager Mr. G. A. Reed W t;uclear Operations and Maintenance Manager of fluelear Operations Virginia Electric and Power Company Wisconsin Electric Power Company P. O. Box 26666 Point Beach fluclear Plant Richmond, Virginia 23261 6610 Nuclear Road Two Rivers, Wisconsin 54241 cc: J. T. Rhodes E. A. Baum jcc: D. K. Porter J. L. Wilson S. Burstein L. M. Girvin ' C. W. Fay J. L. Perkins D. B. Ralsten W ~ F. M. A111 good C. A. Lins W W. R. Cartwright ~ V. W. Lockman W _ Mr. D. C. Hintz, Plant Manager. Mr. N. E. Wandke, Superintendent Wisconsin Public Service Corporation Comonwealth Edison Company Kewaunee Nuclear Power Plant Zion Station Route #1, P. O. Box 48 101'Shiloh Boulevard Kewaunee, Wisconsin 54216 Zion, Illinois 60099 jcc: C. W. Giesler Jcc: J. D. Deress M. E. Stern T. R. Tram C. R. Luoma h*,g*3t p, g g er K. H. Weinhauer J. S. Bitel C. A. Lins W _ F. A. Palmer J. J. Marianyi F. D. Hurd Mr. J. D. Woodward, Manager D. L. Peoples Operating Plants Service W. H. Kiefer Westinghouse Nuclear Belgium J. A. Johnson 73 Rue de Stalle C. M. McKenzie 1180 Brussels, Belgium jcc: R. M. Shepard l Mr. F. P. Tierney, Jr., Plant Manager Prairie Island Nuclear Generating Station Northern States Power Company Route #2 Welch, Minnesota 55089 jec: E. L. Watz1 G. T. Goering . l D. E. Gilberts L. R. Eliason L. O. Mayer I F. M. Sovis W l RDISION 3 MAY 21, 1982 l l}}

ML20065G115: Difference between revisions

Latest revision as of 20:24, 31 May 2023

Contents

Text

SUMMARY

Dearter 1965) ,

Dear Dr. Linnemamann:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Mr. Gary:

Dear Mr. Jones:

Dear Sir:

Dear Mr. Clements:

Dear Sir:

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ML20065G115: Difference between revisions

Latest revision as of 20:24, 31 May 2023

Text

SUMMARY

Dearter 1965) ,

Dear Dr. Linnemamann:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Sir:

Dear Mr. Gary:

Dear Mr. Jones:

Dear Sir:

Dear Mr. Clements:

Dear Sir:

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