ML20027C304
| ML20027C304 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/12/1982 |
| From: | Blauer H, Cordaro M, Rivello J LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20027C225 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8210150250 | |
| Download: ML20027C304 (60) | |
Text
. _.
LILCO, October 12, 1982 l
5 i
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board s
l In the Matter of
)
l
)
LONG ISLAND LIGHTING COMPANY
) Docket No. 50-322 (OL) j
) (Emergency Planning --
l (Shoreham Nuclear Power Station,
) Phase I) t Unit 1)
)
TESTIMONY OF H. MARK BLAUER, MATTHEW CORDARO, AND JAMES RIVELLO i
ON BEHALF OF THE LONG ISLAND LIGHTING COMPANY ON PHASE I EMERGENCY PLANNING CONTENTION EP 7(B) --
ABILITY TO AUGMENT WITHIN 30 MINUTES I
PURPOSE The purpose of this testimony is to respond to Suffolk County's Contention EP 7(B), which suggests that LILCO is not able to augment its onsite staff quickly enough in an emergency.
This testimony will show that, apart from i
augmentation, the on-shift staffing at Shoreham has been 4
planned to be adequate to handle the emergencies for which the emergency plan is designed.
Morever, LILCO will supply senior management personnel with beepers so that they can be reached quickly; personnel assigned the role of Emergency Director will have portable radios for their cars so that they can nm....----
8210150250 821012 PDR ADOCK 05000322 T
. communicate with the station en route.
Finally, LILCO has done a survey of its employees' travel times to establish that those employees can get to the station in a timely manner.
Attachments to this Testimony:
7(B)-1 Resume of Mark Blauer 7(B)-2 Resume of 14atthew Cordaro 7(B)-3 Resume of James Rivello 7(B)-4 LILCO Emergency Plan, pages 5-1 through 5-8 and Figures 5-2 through 5-6 7(B)-5 SP 69.009.01 7(B)-6 Table B-1 from NUREG-0654 7(B)-7 Letter from William J.
Dircks to FJ4C, Inc.,
October 26, 1981 7(B)-8 Pages 19-20 from NRC Staff Recommendations, SECY 82-111 7(B)-9 Response Time Survey
/
~
LILCO, October 12, 1982 k
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing' Board In the Matter of
)
)
~
1 LONG ISLAND LIGHTING COMPANY _
) (Emergency Planning --
) Docket No. 50-322 (OL)
(Shoreham Nuclear Power Station,
) Phase I)
Unit 1)
-)
7 TESTIMONY OF H.
MARK BLAUER, MATTHEW CORDARO, AND JAMES RIVELLO ON BEHALF OF THE LONG ISLAND LIGHTING COMPANY ON PHASE I EMERGENCY PLANNING CONTENTION EP 7(B)
ABILITY TO AUGMENT WITHIN 30 MINUTES Q1.
Will the witnesses please identify yourselves?
A1.
[Blauer]
My name is Mark Blauer.
My business address is 175 East Old Country Road, Hicksville, New York 11801.
I am LILCO's Emergency Planning Coordinator and Chairman of LILCO's Emergency Planning Task Force.
A statement of my professional qualifications is attached (Attachment 7(B)-1).
[Cordaro]
My name is Matthew Cordaro.
I am Vice President, Engineering for LILCO.
My business address is 175 East Old Country Road, Hicksville, New York 11801.
A copy of my professional qualifications is
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l b,.
f attached (Attachment 7(B)-2).
My role in emergency Jplanning is to ensure that LILCO's emergency planning n_eeds are being met and that management is kept apprised of emergency planning needs and problems.
[Rivello]
My name is James Rivello.
My business address is Shoreham Nuclear Power Station, P.O. Box 628, Wading River, New York 11792.
I am employed by LILCO as Plant Manager of the Shoreham Station.
A copy of my professional qualifications is attached to this testimony (Attachment 7(B)-3).
Q2.
What does Contention EP 7(B) say?
A2.
[All witnesses]
Contention EP 7(B) reads as follows:
B.
Table 5-1 does not clearly demonstrate LILCO's ability to augment its staff within 30 minutes of declaration of an emergency and is not in compliance with Table B-1 of NUREG 0654.
Q3.
Where in the LILCO emergency plan is augmentation of onsite staff discussed?
A3.
[Blauer, Rivello]
In chapter 5, particularly pages 5-1 through 5-8 and Figures 5-2 through 5-6.
These parts of the pian are Attachment 7(B)-4 to this testimony.
The relevant procedure, SP 69.009.01 (Attachment 7(B)-5),
gives the notification procedure for all emergency levels and lists personnel who would be called to augment the emergency response organization.
e
. Q4.
What do Table 5-1 and Table B-1 provide?
A4.
[All witnesses]
Table 5-1 has been deleted from the LILCO emergency plan.
Table B-1 from NUREG-0654 (Attachment 7(B)-6) is now included as Figure 5-6 in the LILCO plan and ic attached to this testimony (as part of (B)-4).
Table B-1 is entitled " Minimum Staffing Requirements for NRC Licensees."
It has a column for on-shift personnel and other columns for personnel to be added within 30 minutes and 60 minutes.
QS.
What personnel does LILCO presently have on shift at all times?
AS.
[Rivello]
Typically many people are working on the site at any given time.
Even when this is not the case, the minimum shift manning (a total of 10) is as follows:
1 Watch Engineer, 1 Watch Supervisor, 1 Nuclear Station Operator, 1 Nuclear Assistant Station Operator, 3 Equipment Operators, 1 Shift Technical Advisor, and 2 Health Physics / Rad Chem Technicians.
In addition, at least five shift security personnel are on duty at any given time.
This on-shift organization is described in sections 5.1.1 and 5.2 and illustrated in Figures 5-2 and 5-3 of the LILCO plan (see Attachment 7(B)-4).
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_4 Q6.
What support is provided to the shift personnel upon activation of the Technical Support Center (TSC)?
A6.
[Rivello]
The primary ini'ial support is the relief of the Watch Engineer as Emergency Director by the responding Emergency Director.
This reduces the administrative responsibilities of the Watch Engineer in 4'
the areas of communications to outside agencies (e.g.,
State, County, and media personnel) and verification of emergency actions taken by the on-shift complement (e.g., Health Physics / Rad Chem Technicians, Security, Shift Technical Advisor).
Additionally, the i
communication transfer frees one equipment operator to perform operational duties.
Q7.
How did you determine which accident scenarios would be l
most demanding of the on-shift personnel?
A7.
[Rivello]
To determine what personnel would be required j
within 30 and 60 minutes, we reviewed the events involved in all Emergency Action Levels (EAL's).
Using the relevant emergency procedures, we reviewed what operator actions would be required within 30 and 60 minutes, setting time zero at the points where the emergency procedures require the Watch Engineer to classify the events.
I
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5-i Q8.
What accident scenario was most demanding of site personnel?
i A8.
(Rivello]
The fire in the Control Room was the most i
demanding.
The reason is that by federal requirements one operationally qualified person must be on our fire t
brigade.
This prevents our Watch Supervisor from performing operations duties for approximately 30 minutes.
Also, in our review of this scenario we assumed evacuation of the Control Room; thus we assumed that we had to relocate to, and function from, the Remote Shutdown Panel.
This relocation was accomplished in less than 45 minutes in our scenario; it could usually be done more quickly, but our scenario used the worst-case time.
i Q9.
Are you saying, then, that the on-shift personnel, j
without augmentation, can handle any of the emergencies covered by the LILCO plan for at least 60 minu!.es?
i A9.
[Rivello]
Yes.
Q10.
Is there any NRC requirement to augment onsite emergency response personnel within 30 minutes and 60 minutes?
A10.
[Blauer]
No.
Table B-1 is not a requirement.
A letter l
of October 26, 1981, from the NRC's William J.
Dircks to KMC, Inc. (Attachment 7(B)-7 to this testimony) in pertinent part states:
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- [C]onsistent with our policy for Regulatory Guides, we regard the Table B-1 criteria as having the same level of authority as a Regulatory Guide.
(Revision 2 to Regulatory Guide 1.101 is now in publication which incorporates NUREG-0654 by reference).
Facilities whose staffing augmentation capabilities meet the Table B-1 criteria would be acceptable.
Those facilities which do not meet these criteria will be reviewed on a case-by-case basis.
In addition, pages 19-20 of the "NRC Staff Recommendations on the Requirements for Emergency Response Capability," SECY 82-111 (Attachment 7(B)-8 to this testimony), describe the Staff's position regarding augmentation of emergency response facilities within 30 and 60 minutes:
The TSC [ Technical Support Center] will be:
9.' bt$ffed by sufficient technical, l
engineering, and senior designated licensee officials to provided needed support, and be fully operational within approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after activation.
t Qll.
What measures has LILCO taken to meet the objectives of Table B-l?
2 1
A)).
[Blauer, Rivello]
We have instituted a duty officer system; that is, personnel who would be needed to augment the onsite staff are required, on a rotating basis, to be listed on a duty roster and to be available i
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to come to the site if called.
Senior management personnel are assigned pagers
(" beepers") to ensure their prompt notification.
Additionally, those people who have been designated to assume the Emergency Director role will have two-way radios installed in their cars, permitting direct communication with the Main Control Room; these radios will allow the Emergency Director to be briefed on the status of emargency operations before his arrival on site, expediting the activation of the TSC.
Also, a conference call capability has been provided so that a single phone call from the Control Room will connect several key personnel at once.
Automatic card dialer capability allows the communicators at the site to dial the offsite personnel simply by inserting a card into the phone; this feature both speeds dialing and eliminates error.
Finally, the LILCO personnel who would be called upon to come to the site have been polled, and the times it takes them to get to the site, during normal commuting times, are listed in Attachment 7(B)-9.
Q12.
Do you believe, then, that LILCO satisfies the
" objectives" of Table B-l?
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[Blauer, Rivello]
Yes, based on the measures described above and the response times shown in Attachment /(B)-9.
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- . y (B)
-1 t
PROFESSIONAL QUALIFICATIONS H. MARK F LAUER Chairman, Emergency Planning Task Force
~
Emergency Planning Coordinator LONG ISLAND LIGHTING COMPANY My name is H. Mark Blauer.
My business address is Long Island Lighting Company, 175 East Old ' ountry Road, Hicksville, New York 11801.
I am Chairman of the Emergency Planning Task Force and Emergency Planning Cocrdinator In this capacity, I report to the Vice Presdient, Nuclear, and the Vice President, Engineering.
I also report to the Mana.or, Nuclear Engineering Department.
My duties include overall ttchnical and adminis-tration responsibility for the Emergency Planning Task Force.
The Task Force is responsible for developing and maintaining the Shoreham Nuclear Power Station Emergency Plan; Emergency Training curriculum, manuals, and lesson plans; qualification and selection of emergency ;esponse personnel; Emergency Plan procedures; onsite and offsite emergency support facilities; the Prompt Notification System; the interfacing with Federal (NRC, DOE, FEMA, Coast Guard), State (Department of Health, Disaster Preparedness Commission) and Local (Suffolk County,
i
. hospitals and fire departments) authorities as well as other nuclear industry support groups (INPG)..
I received my Bachelor and Master of Science degrees from the State University of New York at Stony Brook in 1968 and 1971, respectively.
I received my Doctorate in Nuclear Chemistry from the University of Glasgow, Scotland in 1977.
From 1971 to 1s75 I was a Research Assistant '(U.S.
equivalent:
Assistant Professor) at the University of Glasgow teaching nuclear chemistry and researching low-level tritium techniques.
I was a Research Assistant (U.S. equivalent:
Assistant Professor) at University College, London from 1975 to 1977 teaching isotope geology, researching major and trace ele-techniques and acting as consultant to several water auth-ment orities.
During this period the following were published:
- Anderson, A.,
Blauer, H.
M.
and Baxter, M.S. (1977). A controlled power supply for the electrolytic enrichment of tritium, J.
Physics, V10, pp. 1286-1294.
Beckinsale, R.D.,
- Bowles, J.F.W.,
Pankhurst, R.J.,
- Wells, M.K.
and Blauer, H.M.
(1977).
Rubidium-strontium age studies and geochemistry of acid ve. ins in the Freetown complex, Sierra Leone, Mineralogical Magazine, V41, pp. 501-511.
- Blauer, H.M.,
- Baxter, M.S.
and Anderson, A.
(1978).
An improved technique for the electrolytic enrichment of tritium, Analyst, V103, pp. 823-829.
- Hope, C.A.,
- Blauer, H.M.
and Reiderer, J.
(1980).
Recent analysis of 18th dynasty pottery in "Studien zur Altagyptischen Keramic," edited Dorothea Arnold, Philip von Zabern, Mainz.
In 1977 I returned to the United States and assumed the
. l 1
position of Assistant Professor at the University of Pittsburgh, Department of Radiation Health from 1977 to 1980.
I taught radiation health, radiation chemistry and nuclear chemical separation techniques; researched bioassay techniq3tes and low-level environmental measurement techniques; directed an EPA certified radio-chemical laboratory; and consulted with several major uranium producers.
During this period khe fol-lowing were published:
Dennis, Nancy A.,
- Blauer, H. Mark, and Kent, Jacqueline E.
(1981).
Dissolution fractions and half-times of single source yellowcake in simulated lung fluids, Health Physics, V41.
l
- Culp, P.
and Blauer, H.M.
(1979).
Dissolution rates of radionucleides from coal and coal ashes, Twenty-fourth Annual Meeting of the Health Physics Society, Philadelphia, PA.
- Dennis, N.A.
and Blauer, H.M. (1979).
Dissolution rates of uranium in yellowcake in simulated lung fluids, Twenty-fourth Annual Meeting of the Health Phy.>ics Society, Philadelphia, PA.
Padecanin, T.
and Blauer, H.M. (1979).
Comparison of uranium urinalysis methods, Twenty-fourth Annual Meeting of the Health Physics Society, Philadelphia, PA.
- Blauer, H.M.
and Dennis, N.A. (1979).
Dissolution rates of uranium from single source yellowcake in both simulated interstitial and surfactant lung fluids, Twenty-fifth Annual Conference on Bioasesy, Enviromental and Analystical Chemistry, Las Vegas, N.Y.
Maits, A.H.
and Blauer, H.M.
(1980).
Pure uranium oxides:
their dissolution rates plus relationship to yellowcake dissolution characteristics, Twenty-fifth Annual Meeting of the Health Physics Society, Seattle, WA.
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- Blauer, H.M.
and Brown, S.H.
(1980).
Physical and chemical parameters affecting dissolution I
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. characteristics of yellowcake in simulated lung fluids, Twenty-fifth Annual Meeting of the Health Physics Society, Seattle, WA.
- Brown, S.H.
and Blauer, H.M.
(1980).
Characterization of yellow-cake (U308) from multiple sources and some implications regarding uranium mill bioassay, Twenty-fifth Annual Meeting of the 3ealth Physics Society, Seattle, WA.
From 1980 to 1981 I was Environmental Scientist at Three Mile Island Nuclear Generating Station responsible for audits, the Radiological Environmental Monitoring Program, offsite dose calculations and health effects studies.
During this period the following positions and procedures were writ-ten:
- Blauer, H. Mark (1981).
Three Mile Island Nuclear Station, Comments on the Articles "The First Casualty at TMI" and "The Lethal Path of TMI Fallout" by Ernest J.
Sternglass.
Blauer, H. Mark (1981) TMI Enviromental Controls REMP Procedure, Determination of REMP investigation levels and subsequent actions, ECP 1507, Rev.
1.
Blauer, H. Mark (1981) TMI Environmental Controls Emergency REMP Procedure, operating procedure for the CRT, ECP 1601, Rev.
O.
Blauer, H. Mark (1981) TMI Environmental Controls Emergency REMP Procedure Determination of Off-Site Dose, ECP 1602, Rev.
1.
Blauer, H. Mark (1981) TMI Environmental Controls Drocedure Ge(li) detector system using series 80, ECF
_719, Rev.
O.
I joined LILCO in 1981 as Senior Scientist, Nuclear Licensing Division.
My responsibilities include providing sup-port to corporate and plant staff in the areas of Radiation
In 1982 I became Chairman of the Emergency Planning Task Force responsible for all technical and administrative functions.
During this period, the following courses and procedures were prepared:
General Physics - BWR Familiarization Course (1 week)
LILCO - BWR Familiarization Course (2 weeks)
Blauer, H. Mark (1981) REMP data receipt and running tables, RP 4.2, Rev. O j
- Blauer, H. Mark (1981) Anomalous data results - LLD and
)
positive value exceptions, RP 4.3, Rev. O
- Blauer, H.
Mark (1982) Acceptance Criteria, RP 4.4, Rev. 0 1
- Blauer, H. Mark (1982) Determination of REMP investiga-tion levels and subsequent actions, RP 4.5, Rev.
O.
I am certified by the American Chemical Society and a member of the American Geophysical Union and Health Physics 1
Society.
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. (B) - 2 4
PROFESSIONAL QUALIFICATIONS MATTHEW C.
CORDARO Vice President of Engineering LONG ISLAND LIGHTING COMPANY My name is Matthew C.
Cordaro.
My business address is j
Long Island Lighting Company, 175 East Old Country Road, Hicksville, New York 11801.
I am currently Vice President of Engineering and have held this position since the spring of 1978.
As Vice President of Engineering, I am responsible for all of LILCO's engineering activities.
This includes responsi-bility in the areas of facility planning and engineering for nuclear and fossil electric generating plants, as well as elec-tric and gas transmission and distribution systems.
In addi-tion, I am responsible for assessing the environmental impacts of all LILCO operations.
I received my Bachelor of Science degree in Engineering 4
i Science from C. W.
Post College in 1965.
I received my Master of Science degree in Nuclear Engineering from New York University in 1967. I received my Doctorate in Applied Nuclear Physics from the Cooper Union School of Engineering and Science a
in 1970.
I was awarded the Atomic Energy Commission Special I
i i
Fellowship in Nuclear Science a.-d Engineering.
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My past professional affiliations include a position as Guest Research Associate at Brookhaven National Laboratory, Adjunct Associate Professor of Nuclear Engineering at Polytechnic Institute of New York and Adjunct Assistant Professor at C.
W. Post College.
I joined LILCO in 1966 and from 1966 to 1970 I held the positions of Assistant Engineer (1966), Associate Engineer (1967), Nuclear Physicist (1968) and Senior Environmental Engineer (1970).
In these earliest positions with LILCO I was involved as a principal in all phases of nuclear power plant design, licensing and fuel management.
I was also a lead wit-ness for the Company in Federal and State licensing proceedings for the Shoreham and Jamesport Nuclear Power Stations.
In 1972 I assumed the position of Manager of Environmental Engineering.
In this capacity I was responsible for the environmental impact of all LILCO operations.
This position involved the supervision, administration and direction of all environmental programs aimed at demon: trating compliance with applicable standards.
I am a member of a number of related professional organizations including: the Board of Directors, Adelphi University's Center on Energy Studies; and the Council of Overseers, C. W.
Post College.
Other related professional _
affiliations are:
the Technical Resourcec Advisory Council to the New York State Department of Environmental Conservation; the New York Power Pool Environmental Committee; Advisory Task Forces and Committees of the Atomic Industrial Forum; the Long Island Association of Commerce and Industry Environmental Committee; the Advisory Board to Environmental Technology Seminar; the Environment and Energy Committee of the Edison Electric Institute; and the HSA Environmental Task Force.
I have also been a member of the Research Planning Advisory Committee for the New England River Basins Commission Study of Long Island Sound, the Marine Advisory Council to the New York State Sea Grants Seminar, and the Nassau-Suffolk Health Systems Agency (HSA), Suffolk County Council.
In addition, I am a member of the American Nuclear Society, the Health Physics Society and the Environmer".al Technology Seminar.
My most recent publications include a paper on methodology for power plant site selection, papers presented at the World Energy Conference on space heating alternatives and power plant cooling systems, a paper related to power plant waste heat utilization, and a paper on the transportation of nuclear wastes.
I have also published journal articles in the fields of environmental science and nuclear science, as well as...
numerous studies and reports related to the environmental effects of energy production.
I recently testified before Congressional Committees on Nuclear W ste Transport and the Economics and Environmental Impacts of Coal Utilization...
. (B) - 3 e
PROFESSIONAL QUALIFICATIONS i
JAMES RIVELLO Plant Manager LONG ISLAND LIGHTING COMPANY i
My name is James Rivello.
My business address is Long l
Island Lighting Company, Shoreham Nuclear Power Station, P.
O.
Box 628, Wading River, New York 11792.
I am Plant Manager of the Shoreham Nuclear Power Station and have held this position since 1978. I am responsible for managing all plant activities in a manner which provides efficient overall plant operation and ensures the generation of the maximum amount of electric power at the highest plant efficiency, reliability, and availa-bility. This objective must be achieved at the most economical cost consistent with prudent management.
I am also responsible for ensuring that all plant activities are conducted in compli-ance with plant technical specifications, licenses, QA, nuclear i
safety, radiation control, health physics, environmental, secu-i rity, and other factors.
Plant operations must meet Nuclear
[
Regulatory Commission (NRC), Federal, State, and Company
(
Requirements, with the minimum radiation exposure to the gen-l eral public and employees.
I delegate responsibility to four l
i subordinate Engineers.
Each of these Engineers ic responsible
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! for a particular facet of the plant operations requiring specialized knowledge and ability, and for coordinating their activities with those of the other Engineers to create a re-sponsive and cohesive plant organization.
I represent the Shoreham Plant in engineering, construction and testing activi-ties as well as technical licensing efforts with federal, state and local regulatory groups.
I formulate all policies to oper-ate the nuclear plant within the requirements specified in the Technical Specifications, FSAR, Title 10 Code of Federal Regulations and other industry standards and guidelines.
In the event of an accident I am cmergency Director of the Plant.
i I also chair both the Review of Operations Committee, which ap-proves the performance of all safety related aspects of the plant, and the Joint Test Group during the Preoperational Phase to overview the Startup Staff Test Program.
I graduated from Manhattan College in 1963 with a Bachelor of Mechanical Engineering degree.
I completed two years of the Nuclear Engineering Masters Program at Long Island I
University C.
W.
Post Campus (1967-69).
In 1973 I completed specialized nuclear courses at the University of Michigan.
I have also completed courses conducted by the General Electric Company in BWR Technology (August 1973) and BWR Simulator and i
l have received Senior Reactor Operator Certification (December 1973).
i.
i Before assuming my present position, I was Startup i
Manager for the Shoreham Station (1974-1978).
I developed the Startup Program, the Implementing Manual, and the Checkout and Initial Operations Test Program.
My responsibility was to co-ordinate engineering, construction, and plant staff activities as they relate to system completion regarding design, construc-tion, documentation of testing and compatibility of generated data in the respective organizations. I directly managed six Engineers, including the S&W lead Advisory Engineer, the General Electric Company Site Operations Manager, and four Lead Startup Engineers.
From December 1973 to November 1974 I was assigned to Commonwealth Edison Company's Dresden Nuclear Station as a Technical Staff Engineer (five months) and Project Engineer (six months).
As a Technical Staff Engineer, one of my major duties was coordination of a refueling outage of D-3, not in-cluding basic maintenance work.
I worked directly for the Lead Nuclear Engineer and Assistant Plant Manager.
I participated in post refueling outage startup testing which included neutron monitoring overlap tests, flux shaping safety relief valve ca-pacity tests, etc.
I also provided substantial input to plan-ning for the refueling outage of D-2 as a result of my past ex-perience on D-3.
I performed all activities of Technical Staff Engineer from unusual event reports (abnormal occurrences) to major and minor modification safety evaluations, engineering,
l i procurement, and operational testing (e.g.,
off-gas system installation and startup, SBLC and HPCI, surveillance tests, shutdown margin tests, fuel sipping, RC pump " freeze plug" re-pair, integrated leak rate test, jet pump calibration, refuel-ing jib crane replacement, control rod friction testing, nuclear materials safeguards program, hydraulic snubber inspec-tions, torus level instrumentation replacement, e tc. )'.
As a Project Engineer, I was directly responsible for the final construction schedule and initial operations testing of a major high conductivity drain vaste concentra-tion / evaporation system.
I conducted and evaluated all tests on this system and recommended and implemented changes and met the EPA in-service date.
I coordinated operator training on system operations and ran the system for one month under heavy demand conditions.
Throughout this assignment, I performed many substantial projects for the onsite review committee and i
special nuclear systems testing and evaluations including, for example, evaluation of off-gas system explosions and installa-tion of new Safety Relief Valves (Target Rock).
From April 1971 to : Jay of 1973 I was Chief Engineer (Assistant Plant Manager) of a multi-unit 400 MW fossil fueled station.
From June 1963 to May 1971 I held supervisory posi-tions in four different fossil fueled stations, following the
- l normal progression of Associate Engineer (entry level for engineers), Plant Engineer, Operating Engineer, Maintenance and I&C Engineer.
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. I am a member of the New England Nuclear Superintendents Association, the Edison Electric Institute Nuclear Operations Committee, and the American Nuclear Society.
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,- (B)
-4 5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES I
Using the normal operating organization (Fig. 5-1) as a base, this section of the plan describes the activation of the emergency organization and the assignment of authority and responsibility for functional areas of the emergency response.
The latter part of this section describes the functions of offsite organizations and their emergency roles.
5.1 Normal Operation Organization Responsibility for LILCO nuclear cperations is assigned to the vice President-Nuclear who reports to the Senior Vice President-Transmission, Distribution and Operations. The Vice President-Nuclear is assisted by the Shorehan Plant Manager who is responsible for the.tation organization including technical support, quality assurance, engineering and operations.
This organization is shown in detail in Figure 5.1.
Furthermore, as stated in Section 13.1.2 of the Shoreham Nuclear Station (SNPS) FSAR, the Station Organization will consist of a minimum of 165 full-time employees functioning in one of 11 main sections reporting through their respective Section Heads to one of three divisions headed by either the Chief Operating Engineer, Chief Technical Engineer, or Technical Support Manager who reports to the Plant Manager.
The operating Quality Assurance Division reports to the Plant Manager l
through the Operating Quality Assurance Engineer, as described in Section I
17.2 of the FSAR.
The Maintenance Section of the station will have a minimum of 26 men experienced in mechanical and electrical maintenance of large steam-electric generating stations. The force will be supervised by i
l the Maintenance Foreman who in turn reports to the Maintenance Engineer.
This number of maintenance personnel will be adequate for normal main *.enance, but will be supplemented by additional competent maintenance personnel from other LILCO power stations or organizations, or outside contractors, as may be required. Supplemental maintenance personnel will not work on nuclear systems unless qualified.
The technical sections will consist of a Chief Technical Engineer, with a minimum staff of 39 engineers and technicians who will function in the areas of instrumentation and control, reactor physics, conventional chemistry, radicchemistry, radiological protection, fuel management, plus overall reactor coolant system and station performance.
The technical support staff will consist of a Technical Support Manager with a minimum staff of 8 engineering and technical personnel who will functions in the areas of NRC compliance, modification coordination, in-service inspection coordination, document review, and non-routine testing.
1 l
The Operating Section of the station will include a minimum of 32 supervisors and operators and will be responsible for operation of the l
station.
The station will have a Watch Engineer directing the operations l
of each shift through the Watch Supervisor Nuclear Station Operator and i
Nuclear Assistant Station Operator. The Watch Engineer will report to the operating Engineer.
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The Watch Engineer is responsible for overall operation of the unit durir:g his assigned shift.
He directs the activities cf station personnel assigned to his shift and is cognizant of maintenance and operations activities being performed while he is on duty. The Watch Engineer on duty has both the authority and the obligation to shut down the unit if in his judgment, conditions warrant this action.
1 5.1.1 on Shift Organization 4
The normal operating shift (Fig. 5-2) consists of 10 individuals and security personnel. The Watch Engineer, who holds a Senior Reactor Operator (SRO) license, is in direct charge of all plant operations during his assigned shift and is directly responsible for the actions of his crew. Each shift crew consists of the following individuals:
one Watch Supervisor who also holds an SRO license, a Nuclear Station Operator and a Nuclear Assistant Station Operator both possessing Reactor Operator (RO) licenses, and three Equipment Operators.
Technical support assigned to each operating shift consists of a Radiation Protection Technician, A Radiation Chemistry Technician and a Shift Technical Advisor.
Individual responsibilities for normal operation are defined in administrative procedures.
When initiating conditions exist that result in one of the EALs being reached, the Watch Engineer has the responsibility and authority to declare that an emergency situation exists and to take imnediate action in accordance with written operating procedures to mitigate the consequences the emergency. He will assign the appropriate emergency classification and initiate the necessary Implementing Procedures.
l i 5.2 Emergency Response Organization The LILCO emergency response organization will initially consist of the on-shift personnel as shown in Figure 5-3.
Depending upon the emergency classification declared this emergency organization will activate the Alert Emergency Response Organization shown in Figure 5-4 or the Site Area and General Emergency Response Organization shown in Figure 5-5.
Required response times are noted on the organization charts. Table 5-1 correlates SNPS emergency organization with Table B-1 of NUREG-0654. This section details the assignment of the functional areas of the emergency response to the on-shift and augmented emergency organizations.
Detailed job descriptions for emergency response personnel are contained in the Emergency Plan Implementing Procedures.
Emergency respense organization positions will be assigned to qualified LILCO personnel performing similar functions at corresponding levels of responsibility within the normal operating organization. Qualification of personnel will be in accordance with the training requirements detailed in the Emergency Plan Training Manual.
5.2.1 Emergency Direction and Control The r esponsibility for emergency direction and control, emergency classification, the decision to notify and recommend offsite protective actions and commitment of corporate resources is held I t 5-2 1
l 4
3
mmmms n1 SNRC-764 c,
The Watch Enginscr la responsible for avsrnll cpiration of the unit during j
his nooignsd shif t.
En directo tha activitisc of ctation partonnel assigned i
to his shif t and is cognizant of maintenance and operations activities being performed while he is on duty. The Watch Engineer on duty has both the authority and the obligation to shut down the unit.if in his judgment, conditions warrant this action.
i 5.1.1 On Shif t Organization The normal operating shif t (Fig. 5-2) consists of 10 individuals and security personnel.
The Watch Engineer, who holds a Senior Reactor Operator.(SRO) license, is in direct charge of all plant operations during his assigned shif t and is directly responsible for the actions i
of his crew.
Each shif t crew consists of the following individuals:
one Watch Supervisor who also holds an SRO license, a Nuclear Station
[
Operator and a Nuclear Assistant Station Operator both possessing Reactor " Operator (RO) licenses, and three Equipment,0perators.
i Technical support assigned to each operating shif t consists of a Radiation Protection Technician, a Radiation Chemistry Technician and a Shif t Technical Advisor.
Individual responsibilities for normal operation are defined in administrative procedures.
When initiating conditions exist that result in one of the EALs being reached, the Watch Engineer has the responsibility and authority to declare that an emergency situation exists and to take iz=ediate action in accordance with written operating procedures to mitigate the consequences of the emergency.
He' will assign the appropriate emergency t
classification and initiate the necessary Implementing Procedures.
m.
5.2 Emergency Response Organization i
The LILCO emergency response organization will initially consist of the l
on-shif t personnel as shown in Fugure 5-3.
Depending upon the emergency I
classification declared this emergency organization will activate the Alert Emergency Response Organization shown in Fig. 5-4 or the Site Area and l
General Emergency Response Organization shown in Fig. 5-5.
Availability i
' requirements are identified on these figures for onshif t E=ergency Organization personnel and for those personnel who will augment the onshif t compliment.
The aug=entation of the onshif t personnel shall be accomplished as soon as possible upon notification, and, based upon the average, normal one-way commute 34 time for these personnel, meets the objectives of NUREG-0654 Table B-1 for a 30 to 60 minute response, (Figure 5-6).
i Additionally, senior management personnel are assigned " beepers"'to ensure their prompt notification of emergency situations and TSC Emergency Directors are assigned protable radios for their vehicles to allow com=unications with i
Control Room while in route to SNPS.
Emergency Response organization positions will be assigned to qualified l
LILCO personnel performing similar functions at corresponding levels of responsibility within the normal operating organization. Qualification of r
personnel will be in accordance with the training requirements detailed in i
the Emergency Plan Training Manual.
i i
5-2 l
~
' initially by the Emergency Director and passes to the Response Manager as this individual augments the emergency organization.
The I
responsibilities associated with this position are non-delegatable.
1.
On Shift The Watch Engineer is the Emergency Director and provides emergency direction and control.
He has the authority and responsibility to immediately and unilaterally initiate any emergency actions.
2.
Alert Emergency Augment Upon augmentation tc an Alert emergency organization, the Plant Manager will report to the activated TSC and assume the Emergency Director position from the Watch Engineer.
The Operations Manager will coordinate any repair and maintenance actions between the Control Room and Operations Support Center. The Emergency Planning Advisor No.
2 will assist the Emergency Director in the TSC.
Emergency Planning Advisor No. I will report within 60 minutes and assume direction of the EOF and place the facility in a standby status.
i 3.
Site Area and General Emergency Augment Upon augmentation to either a Site Area or General Emergency, the Response Manager will report to the EOF and assume responsibility for overall direction and control of the response. The Technical t
Support Manager acts as a liaison between the Emergency Director and the Response Manager. The Technical Support Manager is also responsible for providing plant related protective action recommendations to the Response Manager in the TSC.
The Emergency Planning Advisor No. I will assist the Response Manager in his emergency response function.
He will also send, as requested, a representative to each of the government EOCs to assist with communicatiens with off-site authorities.
The Emergency Director retains the authority and responsibility to immediately and unilaterally initiate measures to protect the plant.
5.2.2 Plant Operations During any stage of an emergency, the normal Control Room staff will remain intact. A more senior licensed operator, such as the operation Manager, may assume operational control after completing proper relief procedures.
If while the Watch Engineer is the Emergency Director and the operations Manager or other licensed operator assumes plant operation control from the Watch Engineer, the Watch Engineer will continue to serve as the Emergency Director and maintain overall direction and control.
t 5.2.3 Corrective Actions and Support of Operations i
5-3 r
-_.,.-.,-...-.__.m.-,
_.-_r.
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l 1.
On-Shift
(
The Emergency Director will dispatch qualified personnel available on-shift to perfor.n corrective actions which may j
consist of realignment of plant systems. The Nuclear Assistant Station Operator and the Equipment Operators will be trained to assume responsibilities for these corrective actions.
In addition, the on-shift fire brigade will be provided as per Technical Specifications. At least one person on each shift will be trained in First Aid. Corrective actions will be directed from the Control Room by the Emergency Director.
2.
Alert Emergency Augment Upon augmentation to an Alert Emergency organization, the Operational Support Center (OSC) will be activated.
The OSC Supervisor will coordinate the arrival and dispatch of technicians and keep the TSC informed of available personnel.
The Maintenance Manager in the TSC will direct in-plant corrective actions and repairs.
He will coordir. ate these 4
activities with the Operations Manager to ensure that they do not adversely affect plant operations.
Additional electricians, mechanics,, instrument and control technicians, and fire brigade members will report to the OSC as shown in Figure 5-4.
i 3.
Site Area and General Emergency Upon augmentation to a Site Area or General Emergency, (#litional l(
personnel will be called in to support corrective actions and i
repairs.
The specific personnel will depend upon the type of accident and the technical capabilities required. Thus, only the j
minimum personnel are shown in Figure 5.5.The Design and j
Construction Manager will direct his staff in the contracting and construction necessary to meet the needs of the emergency response.
5.2.4 Technical Support l
l 1.
On-Shift i
The Shift Technical Advisor (STA) is available at all times to assist the Emergency Director in tha determination of plant' cenditions, accident classification and protective action recommendations. The STA is qualified in the area of thermal hydraulics, reactor engineering and plant analysis.
j 2.
Alert Emergency Augment The Plant Technical Manager will report to the TSC and receive a plant status update from the STA. The Plant Technical Manager, supported by several plant staff engineers, shall provide the Emergency Director with an analysis of plant conditions and trends for use in the determination of corrective actions and i
protective actions recommendations.
(
5-4
3.
Site Area and General Emergency Augment
(
The Technical Support Manager (TSM) will be the key individual directing technical and engineering assistance during the emergency response.
Upon reporting to the EOF, he will contact the Plant Technical Manager (or STA) and receive a plant status report and discuss the need for detailed analysis and engineered corrective actions to assist plant staff.
Based upon these discussiehs, the TSM will contact the Technical Support Coordinator at Support Corporate Headquarters, Hicksville, and have him obtain the necessary LILCO, G.E., and S&W support to provide the assistance required.
5.2.5 Radiological Accident Assessment 1.
On-Shift The In-Plant Radiation Monitoring Technician No.
I will be qualified to calculate projected offsite doses and assist the Emergency Director in determining appropriate protective action reccmmendations. The STA and the Radiation Chemistry Technician No.
I will assist in the analysis of source term and plant conditions.
2.
Alert Emergency Augment Dose Assessment Staff Member No. 1 upon reporting to the TSC will relieve the In-Plant Radiation Monitoring Technician No. 1 of his
(
offsite dose assessment duties. An offsite radiation monitoring team will be available for dispatch to measure the quantity and movement of an airborne radioactive release.
The Radiation Protection Manager will relay the dose projection and/or monitoring results to the Emergency Director for use in the determination of Protective Actions.
3.
Site Area and General Emergency Augment The Radiation Control Manager will report to the activated EOF and assume responsibility for offsite dose projections and field monitoring.
Three field monitoring teams, each consisting of a technician and an assistant, will be available via data link and direct communication with the Radiation Protection Manager. The Radiation Control Manager will relay the dose projection and/or monitoring results to the Response Manager for use in determination of protective action recommendations.
5.2.6 Onsite Radiation Protection 1.
On-Shift The In-Plant Radiation Monitoring Technician No. 1 is qualified to evaluate radiological hazards, determine exposure time limits and conduct decontamination as necessary. He may be assisted by Radiation Chemistry Technician No. I who is qualified to cerform
(
4 C,
5-5
l
~
area and personnel monitoring has required.
The Emergency Director will have final authority in determining exposure
(
limitations for emergency response personnel.
2.
Alert Emergency Augment The Radiation Protection Manager (RPM) will direct radiation protection activities from the TSC.
Emergency exposure limits onsite will be approved by either the RPM or Emergency Director.
Additional technicians will be available to conduct in-plant radiation surveys and provide health physics coverage of onsite fire fighting, repairs and corrective actions.
3.
Site Area and General Emergency Augment In addition to the Alert Emergency Augment at these emergency levels, personnel will be available to conduct out-of-plant surveys and provide health physics coverage.
The Radwaste Supervisor is responsible for the storage and handling of both liquid and solid radwaste material during an emergency response.
The Radiation Protection Manager will provide assistance to the Radiation Control Manager as necessary.
5.2.7 Administrative Support 1.
On-Shift The Emergency Director shall delegate administrative
(
responsibilities to available personnel not otherwise involved with the emergency response. These responsibilities consist of distributing appropriate legs, forms and prscedures or other details requested by the Emergency Director.
2.
Alert Emergency Augment Upon activation of the TSC, the Administrative Supervisor shall assume responsibility for providing clerical and logistical support.
He will augment as necessary the emergency response organization with additional personnel not shown in Figure 5-4.
3.
Site Area and General Emergency Augnent The Administration and Scheduling Manager -will provide and coordinate the financial, logistical, clerical and all other administrative support from the EOF.
He will be assisted by personnel at the EOF and Support Corporate Headquarters.
Additional administrative staff will provide. assistance at the TSC and Support Corporate Headquarters engineering group.
These administrative personnel will coordinate their requests, associated with the emergency response effort, through the Administration and Scheduling Manager in the EOF.
'5.2.8 Communications
(
5-6
=
.1.
On-Shift.
1 Upon declaration of an emergency, an Equipment operator will be designated as a Communicator.
The Emergency Director will provide updated information to the Communicator for transmission to offsite authorities. The Communicator will make all required notifications and answer phones and dedicated lines.
2.
Alert Emergency Augment Two communicators will be assigned to the activated TSC. These communicators will handle incoming calls and assume the duty for making required communications with offsite authorities. The Emergency Director, via the Administrative Supervisor, will provide updated information to the communicators. 'The Control Room Communicator will continue to handle the phones in the-Control Room.
3.
Site Area and General Emergency Augment The activated EOF will have three communicators.
Two will support general administration and will handle communications as i
directed by the Administration and Scheduling Manager. A third communicator will support the Radiation Control Manager and his staff by transmitting dose assessment data to offsite authorities. At the TSC, a third communicator will augment the Administrative Supervisor and his staff.
(
5.2.9 Public Affairs 1.
On-Shift The Emergency Communications Liaison will be contacted as part of the initial notification.
This individual will prepare appropriate press releases for plant managemnt and corporate approval. He will also contact additional LILCO public relations personnel as necessary.
2.
Alert Emergency Augment The Emergency Communications Liaison will report to the activated TSC. He will prepare press releases _ based upon ir. formation provided by the Emergency Director.
Press releases will be approved by the Emergency Director and LILCO's Public Affairs Department and distributed to local newspapers and television stations.
3.
Site Area and General Emergency Augment The Emergency Communications Director will be in charge of LILCO's public affairs program from the activated EOF.
The Emergency News Manager and staff will direct operation of the i
Emergency News Center (ENC). They will conduct press conferences which may be attended by the Response Manager and Emergency
+
Communications Director. The Emergency Communications Liaison
,p 5-7
a
~will report to the ENC and assume the position of Emergency Information Supervisor. = Additional staff at Support Corporate
'(
. Headquarters will handle communications with ~ government officials, inquiries from the general public and other details.
5.2.10
' Security The Security force at Shoreham Nuclear Power Station shall respond to an emergency in accordance with the Security Plan.
5.3 Offsite Assistance for Onsite Support
-fire protection ' for the area of Long Island where the plant -is located is provided by volunteer fire departments which operate under the State and County -Mutual Aid Plan.
Under this plan,. nearby departments provide support for the fire department involved in fighting a fire.
Similar arrangements exist for the ambulances associated with these fire.
departments.
The Shoreham Nuclear Power Station is located in the fire district of the Wading River Fire Department. Plans have been developed to provide fire protection. ambulance, and rescue services. A letter of agreement from.the Wading River Fire Department is contained in Appendix B.
The Plans for hospital and medical support are described in Section 6.5.3.
A letter of agreement from the Central Suffolk Hospital is contained in Appendix B.
'(
Although no Federal assistance is expected other than that provided for and specified in the Suffolk County Radiological Emergency Plan, the New. York State Radiological Emergency Preparedness Plan and the Federal Radiological Monitoring and Assessment Plan (FRMAP), should the need arise, the Response Manager has the authority to request any and all Federal assistance considered appropriate for the given situation.
The FRMAP for the Northeast region is located within 10 miles'of the shoreham site, at Brockhaven National Laboratory (BNL), lending itself to
~
fully supporting response in a short period of time. Depending on the nature of the incident, the FRMAP-team shall respond accordingly.
Furthe rmore, because of BNL's proximity to Shoreham, it is concluded that it would serve as a self-supporting center for any additional Federal-emergency support.
5.3.1 Institute of Nuclear Power Operations The Institute of Nuclear Power Operations was. organized by the electric utility industry as a response to the needs of the utility industry 'following the Three Mile' Island accident. The Institute of Nuclear Power-Operations is working in several areas concerning
- training, operating experience evaluation,. criteria development,-
assistance to the utilities, and emergency preparedness.
Assistance is provided to utilities in emergency preparedness to upgrade their capability to respond to an accident. Resources such as equipment and
. manpower.can be coordinated during an accident through the Institute
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Approved / Plant Mgr.:
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i SP Number 69.999.91 Revision 9 Date Eff 7/9/82 i
TPC TPC TPC i
I i
i NOTIFICATIONS i
(
1.0 PURPOSE i
To specify the means by which notification for all emergency levels are made and to delineate personnel who would be called to augment the emergency response organization.
2.0 RESPONSIBILITY The Health Physics Engineer is responsible for ensuring compliance with this procedure.
i i
I l
PPF 1921.699-6.421
~
m,
3.0-DISCUSSION 3.1 Establishment of a quick effective means of notification of an emergency is k critical-part of emergency response.
Primary and secondary modes of
[
communication are provided to insure the availability of proper communications. '
3.2 Preplanned message statements hilow for accurate and complete transfer of l-information.
Persons asking the notification simply read prewritten statements containing the necessary information. Communications guidelines are given in Appendix 12.6.
3.3 The preplanned message forms are filled out by either a Communicator (CR),
EPA #2 (TSC) or EPA #1 (EOF) depending upon the highest facility activated.
The fact sheet is approved by either the Emergency Director or the Response Manager before transmission to appropriate authorities.
r 3.4 Topics covered in this procedures l
E*.E*
1 8.1 Initial Notification 2
8.2 Subsequent Notification 3
1 8.3 Verification 3
8.4 Follow-up Notification 4
4 Appendix 12.1 Notification Fact Sheet, SPF 69.999 91 l
Appendix 12.2 Dose Assessment Fact Sheet, SPF 69.999 91-2 i
Appendix 12.3 Notification Call List, SPF 69 999 91-3 Appendix 12.4 Supplementary Notification Call List, SPF 69 999 91-4 Appendix 12.5 Internal Notification Call List, SPF 69 999 91-5 Appendix 12.6 Communication Cuidelines
- [
Appendix,12.7 NRC Notification Call List, SPF 69 999 91-6 4.0 PRECAUTIONS I
4 l
Only persons authorized by the Emergency Director / Response Manager shall aske
~~
notifications as prescribed in this procedure.
i 1
i i
5.0 PREREQUISITES l
4 An emergency has been classified $n accordance with SF 69.919 91, Classification 4
of Emergency Action Levels.
6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS AND EQUIPMENT i
' Communications equipment as described in Ref. 11.1.
i 1
SP 69 999 91, Rev. 9 i(
07/09/82 Page 2
i 800 PROCEDURE 8.1' Initial Notification 8.1.1 Communicator (CR) fill out a Notification Fact Sheet (Appendix 12.1) an'd submit it to the Emergency Director for approval 8.1.2 Emergency Director provide an approved Notification Fact Sheet to the Communicator and direct him to make the following notifications.
8.1.3 Communicator, using the primary communications mode given in the I
Required Notification Call List (Appendix 12.3) aske the following i
notifications by reading the Notification Fact Sheet..Obtain all.
l information required to fill in Appendix 12.3.
1.
Notify the following personnel:
Plant Manager Vice President - Nuclear Chief Operating Engineer I
4 i
Chief Technical Engineer NOTE:
If these personnel are notified by beeper, do not read off the Notification Fact Sheet.
[
l 2.
Notify the LILCO Ces Systems Operator by means of the Card j
Dialer Phone, so that appropriate corporate persannel can be i
notified in accordance with CIP-1, Corporate Nocifications 3.
NotifyNewYorkState,SuffolkCountyandNewYoriSIste Sourthern District Office by means of the hotline within 15 minutes of classification.
8.1.4 Licensed Operator, make initial notification to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaration by use of the Emergency Notification System
)
l (ENS). After the TSC is activated, this function shall be continuted at that center. Record the notification on Appendix f
12.3.
i NOTE:
The NRC will require the ENS to be continuously amaned if i
they so desire in order to be kept appraised of the l
emergency situation. Provide all information asked for, l
if possible. The operator should ask the NRC if they will speak to a different person so that you can resume i
operational duties.
i 8.2 Subsequent Notifications i
8.2.1 Communicator, using the primary communications mode given in the Supplementary Notification Call List (Appendix 12.4) and record them on the Call List. Obtain all necessary information to i
t k-SP 69 999 91, Rev. 9 I
07/09/82 Page 3 i
l
[
- ~
complcto tha Call List.
NOTE:
Some supplanantary notifications may have to be performed expeditiously for prompt response (e.g. Coast Guard *for T;
waterborne releases). Guidelines for all supplementary notifications are given in Appendix 12.4.
8.2.2 Communicator, call in' additional station personnel as directed.
Use the Internal Notification Call List (Appendix 12.5) for the appropriate on or off-hour time and emergency classification.
8.3 verification 8.3.1 Notifications made by use of dedicated lines require no verification.
8.3.2 All calls ande to offsite agencies by use of commercial lines require the individual receivi.sg the notification to call back and verify that the necessary info rmation has been received.
8.3.3 Notification by beeper of essentf al personnel (Step 8.1.3.1) is verified when these personnel call on the Conference Phone and are i
briefed by the Emergency Director. on the status of plant j
conditions.
8.4 Follow-up Notification 8.4.1 ra==micator (CR) or Emergency Planning Advisor #1 or 2 (TSC or EOF) fill out a Dose Assessment Fact Sheet (Appendix 12.2) and submit it to the Emergency Director / Response Manager for approval.
-(
8.4.2 Emergency Director / Response Manager, provide a completed Dose Assessment Fact Sheet to a Communicator and direct him to make notifications to the agencias on the Notification Call List (Appendix 12.3) and to appropriate agencies on the Subsequent Notification call List (Appendix 12.4).
8.4.3 Communicator, notify the appropriate authorities on Appendix 12.3 and 12.4, using the Dose Assessment Fact Sheec (Appendix ?.2.2).
Obtain the necess:.ry information to complete the Call Lists.
9.0 ACCEPTANCE CRITERIA
\\
N/A 10.0 FINAL CONDITIONS All notifications have been logged on the appropriate call lists.
11.0 REFERENCES
i l
11.1 CIP-3, _ Communications Equipment l
~(
SP 69 999 91, Rev. 9 07/09/82 Page 4
)
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m.r._7.,_,.e.._,,
w_.,,-,e r-m,
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j 11.2 SP 69 919 91, C1mnifientien, et Emergency Actirn Levelo
' 12.0 APPENDICES 12.1 Notification Fac.t Sheet, SPF 69 999.91-1 12.2 Dose Assessaant Fact Sheet, SPF 69.999.91-2 12.3 Notification Call List, SPF 69 999.91-3 12.4 Supplementary Notification Call List, SPF 69.199.91-4 12.5 Internal Notification Call List SPF 69 999.01-5 12.6 Communications Guidelines 12.7 NRC Notification Call List, SPF 69.999.91-6
('
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i SP 69.999 91, Ray. 9 07/09/82 Page 5 i
App ndix 12.1 Part 1 - NOTIFICATION FACT SHEET
{
1.
Date and Timi of Message Transmittal:
Date Time (24 hr clock) 2.
clear Facility providing the initial report:
Indian Pt. No. 2 Fitzpatrick Plant Indian Pt. No. 3 Shoreham Station Ginna Station Other Nine Nile Pt. Unit 1 3.
luportedby:$
Name Title 4.
This is is NOT, an excerise.
5.
Emergency Classification:
I Unusual Event h
Site Area Emergency Alert General Emergency 6.
This Classification occured at Date Time (24 hr clock) 7.
Brief Event Description / Initiating condition:
4 8.
There has NOT been a release of radioactivity.
has been a release of radioactivity to the ATM0 SPHERE.
has been a release of radioactivity to a BODY OF WATER.
has been a GROUND SPILL release of radioactivity.
9.
The release @ is continuing
@ has terminated
@ not applicable.
10.
Protective Actions:
There is no need for protective actions outside the site boundary.
Protective Actions are under consideration.
. Recommended Protective Actions:
l Shelter within miles /or sectors /or ERPA's.
Evacuate within miles /or sectors /or ERPA's.
11.
Weather:
Wind Speed miles per hcur or meters per second.
Direction (from) de:grees.
Stability Class (A-G)
General Weather Conditions (if available)
ED/RM Approval SPF 69 999 91-1
- Rev. 9
(
SP 69 999 91, Rev. 9 07/09/82 Page 6
~.
4 Appendix 12.2 Part II - DOSE ASSESSMENT FACT SHEET.
12.
(
Prognosis for Worsening or Termination of the Emergency:
13.
In Plant Emergency Response Actions Underway:
14.
Utility Off-Site Emergency Response Action Underway:
15.
Release Information
-h ATMOSPHERIC RELEASE Actual FreNeted i
I Date and Time Release Started Duration of Release hrs hrs 4
Noble Gas Release Rate C1/sec C1/sec Radioiodine Release Ci/sec Ci/sec i
Elevated or Ground Release h
WATERBORNE RELEASE 5
Date and Time Release Started Duration of Release hrs bra Volume of Release sal mal Radioactivity Concentration (gross) uCI/al uCi/a1 Total Radioactivity Released C1 Ci a
Radionuclides in Release uCi/al uCi/mi uC1/al uCi/al uCi/a1 uCi/al Basis for release data e.g. effluent monitors, grab sample, composite sample and sample location:
16.
Dose and Hessurements and Projections SITE BOUNDARY Actual Projected I
i 1
l Whole Body Dose Rate mE ar/hr Whole Body Commitment Rea j
Thyroid Dose mRea mRea Thyroid Dose Ram h
PROJECTED OFFSITE 2 Miles 5 Miles 10 Miles t
Whole Body Dose Rate (ar/hr)
Whole Body Dose (Rem)
~
r J
Thyroid Dose Commitment (1 hr Exposure) (area) t Thyroid Dose (Total Commitment)
[
(Rem)
{
17.
Protective Action Recommendations and the basis for that recommendation.
f i
I 1
ED/RM Approval
{
SPF 69 999.91-2, Rev. 9 SP 69 999 91, Rev. 9 07/09/82 Page 7 i
~.. -
..,.,-,_.,.___.,._,y
,,.m_
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..m.
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. App ndix 12.3 REQUIRED NOTIFICATION CALL LIST Message Agency / Person Name of Receiv,ed and Organization Communications Mode Contacted Person Verified Individual Primary / Alternates
- Time /Intitials Contacted Time / Initials 1.
Plant Manager
- 1. Beeper
/
/
- 2. X-291
- 3. Card Dialer Phone 2.
Vice President 1. Beeper
/
/
Nuclear
- 2. 733-4013
- 3. Card Dialer Phone 3.
- Chief
- 1. Beeper
/
/
Operating
- 2. X-292 Engf.,eer
- 3. Card Dialer Phone y
4 4
Chief
- 1. Beeper
/
/
Technical
- 2. X-293 Engineer
- 3. Card Dialer Phone t
5.
Gas Systems
- 1. Card Dialer Phone
/
/
Operator i
NOTE:
These Notifications to be made within 15 minutes of Declaration
- (~
^-
o.
New York State 1. Hotlina
/
/
i Emergency
- 2. NAWAS
[
Operations
- 3. Card Dialer Phone I
7.
New York State 1. Botline
/
/
Southern
- 2. NAWAS I
District Office i
8.
Suffolk County 1. Hotline
/
/
Emergency
- 2. NAWAS Operations
- 3. Card Dialer Phone Center i
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SPF 69.999 91-3, Rev. 9 l
l
?
k SP 69 999.91, Rev. 9 07/09/82 Page 8 I
i
_ _. _ _... _... - - _. ~. - _ _. -. _. _ - - -.
Appendix 12.4 SUPPLEMENTARY NOTIFICATION CALL LIST j
i
. Message Agency / Person Name of Received and Organization /. Communications Mode Contacted Person Verified Individual Primary / Alternates
' Time / Initials Contacted Time / Initials 1.
St. Joseph's
- 1. Card Dialer Phone
/
/
Villa NOTE: Notify for all incidents involving offsite radiological consequences.
2.
U.S. Coast
- 1. Card Dialer Phone
/
/
Cuard NOTE: Notify only for incidents affecting Long Island Sound 3.
Radiation 1.
Card Dialer Phone
/
/
Management Corporation NOTE: Notify only for incidents involving severely contaminated individuals.
j 4.
INPO 1.
Card Dialer Phone
/
/
NOTE: Notify for alert or higher classification U.S. EPA 1.
Card Dialer Phone
/
/
[
NOTE: Notify for all incidents affecting environment.
6.
U.S. Doe 1.
Card Dialer Phone
/
/
FRMAP Team NOTE: Notify only when directed by the Radiation Protection Manager / Radiological Control Manager l
SPF t,9 999 91-4, Rev. 9
(
SP 69 999.91, Rev. 9 07/09/82 Page 9
4 g endix 12.5 INTERNAL NOTIFICATION CALL LIST (IATER)
SPF 69 999.91-5, Rev. 9 1 *
}
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e
)
SF 69 999 91, Rev. 9 07/09/82 Page 10
Appendix 12.6 C0f0RINICATIONS CUIDELINES
- (-
Notify individuals / organizations listed in the Call Lists (Appendices 12.3 or-12.4) using one of the preplanned message forms as follows:
1.
Call each individual / organization using the primary mode of communication.
If the party cannot be contacted using the primary method, use the, alternate method.
~
' ~
2.
If a party cannot be contacted, bypass that party and proceed to the next one on the list. After all notifications have been completed, attempt to contact the bypassed parties. If a party still cannot be contacted, consider other methods such as relaying information through a third party.
3.
ilhen the party answers, identify yourself and inform the individual to obtain the form on which to record the notification. Pause to permit the individual time to obtain the form.
4.
Read the notification, annunciating the information which is to be entered on the form.
5.
After the notification has been completed, ask the individual to read back the notification and, if necessary, correct any errors.
6.
Record the name of the individual and the time of contact on the Notification
.I Call Lists.
~
4 7.
Proceed to the next agency on the Call List until all organizations have been notified.
4 I
SP 69 999.91, Rev. 9 07/09/82 Page 11
App,ndix 12.7-NRC NOTIFICATION CALL LIST Message Agency / Person Name of Received and Organization Communications Mode Contacted Person Verifed Individual Primary / Alternates time / Initials Contacted Time / Initials NOTE:
NRC Notifications (#9 and 10) to be performed by Licensed Operator only.
i Notification to NRC within I hour of classification.
1.
- NRC,
- 1. Emerg. Notification '
/
/
Washington Systen-(ENS)
- Office, Dedicated Phone Bethesda
- 2. Card Dialer Phone 2.
'NRC,
- 1. Emers. Notification
/
/
,f Regional System (ENS)
Office, King Dedicated Phone of Prussia
- 2. Card Dialer Phone l
i I,(.
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t 4
N i
i SPF 69 999 91-6, Rev. 9 l
I SP 69.999.91, Rev. 9 l
07/09/82 Page12 l.
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Tcb12 B-1 MINIMUM STAFFING REQUIREMENTS FOR NRC LICENSEES FOR NUCLEAR POWER PLANT EMERGENCIES (See B.S.)
5 5
Position Title On Capability for Additions y
Major functional Area Location Major Tasks or Expertise Shi f t*
30 min 60 min C"
Plant Operations" and Assessment of Shift Supervisor (SRO) 1 U,
Operational Aspects Shif t Foreman (SRO) 1 Control Room Operators 2
g Aux 111ary Operators 2
Emergency Direction and Shift Technical Advisor, 1**
Control (Emergency Shift Supervisor or Coordinator)***
designated fact 11ty manager Notification /
Notify licensee, State 1
1 2
Consnunicatforf***
local and Federal personnel & maintain consnunication 9
Radiological Accident Emergency Operations Senior Manager w
1 7
Assessment and Support Facility (EOF) Director cf Operational Accident Offsite Cose Senior Health Physics Assessment Assessment (HP) Expertise 1
Offsite Surveys 2
2 Onsite (out-of-plant) 1 1
In-plant surveys HP Technicians 1
1 1
Chemistry / Radio-Rad / Chem Technicians 1
I chemistry Plant System Technical Support Shift Technical Advisor 1
Engineering, Repair Core /Themal Hydraulics 1
and Corrective Actions Electrical 1
Mechanical 1
Repair and Corrective Mechanical Maintenance /
1**
1 Actions Rad Waste Operator 1
Electrical Maintenance /
1**
1 1
Instrument and Control (14C) Technician 1
O
Table B-1 (contd)
Position Title On Capability for Additions Major Functional Area Major Tasks or Expertise Shift
- 30 min 60 min Protective Actions Radiation Protection:
HP Technicians 2**
2 2
(In-Plant) a.
Access Control b.
HP Coverage for repair, corrective actions, search and rescue first-aid & firefighting c.
Personnel monitoring d.
Dosimetry Fire Brigade Local Support Firefighting per Technical Specifications 2**
Local Support Rescue Operations cnd First-Aid Site Access Control Security, firefighting Security Personnel All per and Personnel connunications, personnel Security plan M
Accountability accountability Total 10 11 15 Notes:For each unaffected nuclear unit in operation, maintain at least one shift foreman, one control room operator and one auxiliary operator except that units sharing a control room may share a shif t foreman if all functions are covered.
May be provided by shift personnel assigned other functions.
Overall direction of facility response to be assumed by EOF director when all centers are fully manned. Director of minute-to-minute facility operations remains with s+nior manager in technical support center or control room.
- May be performed by engineering aide to shift supervisor.
4
)
)
UNITE 3 STATES Attachmsnt 7(B) -7
[ ',,, }o NUCLEAR REEULATARY COMMISSION
-y' g
wassmoroN, o. c. rosss E
- i/
OCT 2 61981 i
Dr. Donald F. Knuth President i
KMC, Inc.
q 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 j
Dear Dr. Knatfi~:
)#
This is in response to your letter dated October 5,1981 regarding the capability for rapid augmentation of a nuclear power plant staff in the event of an emergency.
We expect that each utility will expend its best efforts to meet tne augmentation criteria of Table B-1 of NUREG-0654/FEl%-REP-1 with respect to additional skills, such as professional health physics expertise, which may not be present on shift and to assure that enough " hands" are available to perform the nany tasks that would result from an emergency.
Therefore, consistent with our policy for Regulatory Guides, we regard the Table B-1 criteria as having the same level of authority as a Regulatory Guide.
NUREG-0654 by reference)y Guide 1.101 is now in publication which incorporates (Revision 2 to Regulator Facilities whose staffing augmentation capabilities meet the Table B-1 criteria would be acceptable. Those facilities which do not meet these criteria will be reviewed on a case-by-case basis.
Failure to meet the criteria in a particular drill would clearly not call for a civil penalty as indicated in your letter. Repeated failure to meet the design objective (goal) would be cause for the NRC to request utility manage-ment attention to this problem.
The response times listed in Table B-1 are certainly not rigid inviolate requirements as suggested in your letter because weather conditions, for example, could influence arrival times. A treatment of this problem in a recent SER (for the Callaway plant) is enclosed which gives an indication of the staff approach to this matter.
Sincerely, e
William J. Dircks Executive Director for Operations
Enclosure:
Excerpt from Appendix F of the Callaway SER
)
)
ENCICSURE 1 4
EXCERPT FROM APPENDIX F OF THE CALLAWAY SER DATED OCTOBER 1981 "The onsite (minimum) emergency organization for non-normal working hours, backshifts, and holidays is described in the Plan.
Emergency assignments have been made, and the relationship between the emergency organization and the normal staff cocplement are described in the Plan.
Positions and/or titles and qualifications of shift and plant personnel both onsite and offsite who are assigned major emergency functional duties are listed. Minimum sLft 1
manning and shift augmentation are in the Plan and guidance for timely shift augmentation is provided.
The minimum on-shift staffing levels discussed in the Plan meet the objectives of Table B-1 of NUREG-0654. The Plan describes the capability to augment the minimum on-shift staff after declaration of an emergency. This capability meets the design objectives of Table B-1 and is prioritized to provide capability within 30 to 45 minutes and 60 to 75 minutes.
.i The following minimum on-shift expertise will be maintained 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per days one Shift Supervisor (SRO), one Operating Supervisor (SRO), two Unit Reactor i
Operators, two Equipment Operators, two Assistant Equipment Operators, one Instrument-Control Tech., one Radiation-Chemistry Tech., and one Shift Technical Advisor. This makes a total of eleven persons on shift capability of performing all necessary major functions called for in Table B-1.
A person j
on-shift will be qualified to conduct in-plant radiation surveys.
This is L
maintainea 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
Within 30 to 45 minutes, depending on road and weather o>nditions, the additional personnel will be available for communications, in-plant protective actions, i
radiological accident assessment and operational support, and plant system engineering and repair actions. Within 60 to 75 minutes, fifteen additional a
persons will be available to augment the above mentioned functional area.
Because shift augmentation does not conform to the staff guidelines of 30 to 60 minutes, the licensee has committed to an extensive duty officer system to strengthen their existing augmentation capability. Further, periodic unannounced i
drills will be conducted of the system to ensure the design objectives of Table B-1 can be achieved.
Records will be maintained for inspection. The
~
duty officer system will ensure sufficient management and supervisory personnel will be on call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day with a reliable pager system or automatic telephone system. Prioritized shift augmentation procedures will be developed and tested.- In addition to the above, a dedicated Emergency Duty Officer will be maintained 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day who can act as the EPOM.
The staff finds that adequate shift staffing and augmentation capabilities exist 1
and will m'emmine the duty officer system during the preoperational inspection".
i l
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r v.
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- - (B)
-8
)
19 c
Technical Support Center (TSC)
Functional Statement The TSC is the onsite technical support center for emergency response.
When activated, the TSC is staffe'd by p' redesignated technical, engineering, senior management, and other licensee personnel, and five predesignated NRC personnel.
During periods of activation, the TSC will operate uninterrupted to provide plant management and technical support to plant operations personnel, and to relieve the reactor operators of peripheral duties and com:::unications not directly related to reactor system manipulations.
The TSC will perform EOF functions for the Alert Emergency class and for the Site Area Emergency class and General Emergency class until the EOF is functional.
Recommended Reouirements The TSC will be:
1.
Located within the site protected area so as to facilitate necessary interaction with control room, OSC, EOF and other personnel involved with the emergen y.
n 2.
Sufficient to accommodate and support NRC and licensee predesignated personnel, equipment and documentation in the center.
v 3.
ftructurally built in accordance with the National Uniform Suilding Code.
4.
Environmentally controlled to provide room air temperature, humidity and cleanliness appropriate for personnel and equipment.
5.
Provided with radiological protection and monitoring equipment necessary to assure that radiation exposure to any person working in the TSC would not exceed 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident.
6.
Provided with reliable voice and data communications with the control room and EOF and reliable voice communciations with the OSC, NRC Operations j
Centers and state and local operations centers.
7.
Capable of reliable data collection, storage, analysis, display and communication sufficient to determine site and regional status, determine changes in status, forecast status and take appropriate actions.
The '
following variables shall be available in the TSC-(a) ~ the variables in the appropriate Table 1 or 2 of Regulatory Guide 1.97 (Rev. 2) that are essential for performance of T5C
- o functions; and Q
(b) the meteorological variables in Regulatory Guide 1.97 (Pev. 2) for site vic'inity and National Weather Service data available by voice communication for the region in which the plant is located.
]
,,y-20
.o Principally those data must be available that would enable evaluating 1
incident sequence, determining mitigating actions, evaluating damages and determining plant status during recovery operations.
8.
Provided with accurate, complete and current plant records (drawings, schematic diagrams, etc.) essential for evaluation of the plant under accident conditions.
9.
Staffed by sufficient technical, engineering, and senior designated licensee officials to provide needed support, and be fully operational within approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af,ter activation.
10.
Designed taking into account good human factors engineering principles.
S e
o e
e
+
6e O
e
/
'O
.,. p.s Attcch: nt 7 (D).
Response Time Survey c
1 2
3 4
5 Normal Major' functional Position LILCO personnel commute area title or expertise to fill position time Beeper Notifications /
N/A Individual 1 20 min.
no "ommunications Individual 2 20 min.
no Individual 3 30 min.
no Individual 4 40 min.
no Individual 5 45 min.
no Individual 6 75 min.
no Rad Accident Senior Mgr.
Individual 1 30 min.
yes Assessment and Individual 2 30 min.
yes Support of Oper-Individual 3 50 min.
yes ational Accident Assessment Senior Health Individual 1 18 min.
yes Physics Expertise Individual 2 30 min.
yes
-Individual 3 5 min.
yes HP Technicians Individual 1-13 min.
no Individual 2 15 min.
no Individual 3 15 min.
no Individual 4 15 min.
no Individual 5 15 min, no
b,
1 2
3 4
5 Normal Major. functional Position LILCO personnel commute area title or expertise to fill position time Beeper Individual 6 20 min.
no Individual 7 25 min.
r.o i
Individual 8 35 min.
no Individual 9 45 min.
no Rad Chem Individual 1 15 min.
np Technicians Individual 2 10 min.
no 4
Individual 3 20 min.
no Individual 4 30 min.
no Individual 5 40 min.
no Individ.ual 6 45 min.
no Individual 7 45 min.
no Individual 3 45 min.
no Individual 9 60 min.
no Individual 10 60 min.
no Individual 11 60 min.
no Plant System Core / Thermal Individual 1 25 min.
yes Engineering, Hydraulics Individual 2 10 min.
no Repair and Cor-Individual 3 15 min.
no rective Actions Electrical Individual 1 5 min.
.yes Individual 2 45 min.
no
'e
.. 1 2
3 4
5 Normal Major functional Position LILCO personnel commute area title or expertise to fill position time Beeper Mechanical Individual 1 25 min.
no Individual 2 8 min, no Electrical and Mechanics A1 Mechanical
~
Maintenance Individual 1 20 min.
no Individual 2 20 min.
no Individual 3 20 min.
no Individual 4 25 min.
no Individual 5 30 min.
no Individual 6 30 min.
no Individual 7 38 min.
no Individual 8 40 min.
no Individual 9 40 min, no Individual 10 40 min.
no Individual 11 40 min.
no Individual 12 45 min.
no Individual 13 66 min.
no Individual 14 75 min.
no Mechanics B1 Individual 1 4 min.
no Individual 2 7 min.
no Individual 3 10 min.
no 1
Individual 4 15 min.
no J
Individual 5 20 min.
no
~a 1 2
3 4
5 Normal
. Major functional Position LILCO personnel commute area title or expertise to fill position time Beeper Individual 6 20 min.
no:
Individual 7 30 min.
no Instrumentation Individual 1 5 min.
no and Control-Individual 2 8 min.
no Individual 3 20 min.
no Individual 4 20 min.
no Individual 5 25 min.
no Individual 6 25 min.
no Individual 7 25-30 min.
no Individual 8 25-30 min.
no Individual 9 30 min.
no Individual 10 40 min.
no Individual 11 45 min, no Individual 12 45-60 min.
no Individual 13 60 min.
no Individual 14 60 min.
no Individual 15 65 min.
no Individual 16 75 min.
no Individual 17 90 min.
no
.: a