ML20004E957
| ML20004E957 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/12/1981 |
| From: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-3.A.1.2, TASK-TM GL-81-10, NUDOCS 8106160236 | |
| Download: ML20004E957 (11) | |
Text
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i YANKEE AT0 10 ELECTRIC COMPANY i
Qh 1671 Worcester Road, Framingham, Massachusetts 01701
.Yauxes C-} '
,M June 12, 1981 9
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United States Nuclear Regulatory Commission
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Attention:
Mr. Darrell G. Eisenhut, Director
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Division of Licensing
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) USNRC Letter to YAEC dated February 18, 1981 (Generic Letter 81-10)
(c) YAEC Letter to USNRC dated March 27, 1981 (FYR 81-48)
(d) YAEC Letter to USNRC dated January 1, 1981 (FYR 81-6)
(e) YAEC Letter to USNRC dated April 10, 1981 (FYR 81-59)
Subject:
TMI Action Plan Item III. A.l.2, Upgrade Emergency Support Facilities
Dear Sir:
This letter responds to the specific requests in Reference (b) and provides the descriptions of the overall upgraded emergency response facilities design. Each of the items below responds in sequence to the six items for which documentation was requested.
(1) Descriptions of the emergency response f acilities are provided in Attachment A.
The task functions of those individuals required to i
report to those facilities are provided in the Yankee Rowe Emergency Plan submitted in Reference (c).
(2) A closed circuit television monitor has been installed in the Technical Support Center (TSC) with a dedicated camera in the Control Room. This camera is remotely operated from the TSC and will display and transmit plant parameters (see Attachment B) on the Main Control Board (MCB) to the TSC, thereby maintaining the same high degree of instrument quality, instrument accuracy and reliability.
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A computer terminal data link is also established between the Er.ergency Operations Facility, the Framingham office, and the TSC.
To collect and store data in a sequential order from the MCB during an emergency condition, this data must be manually input from the TV camera / monitoring system. Meteorological data which is automatically transmitted to the Westboro Environmental Laboratory may also be accessed for consideration of off-site radiological considerations by this system.
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-.-S U.S. Nuc1 car Rrguistory Comaission June 12, 1981 Attsnticn:
Mr. Darra11 G. Eisenhut, Director Page 2 (3) Power for the TV monitoring system in the TSC is supplied from an emergency power supply. Emergency power is supplied via the emergency diesel generators.
(4) Data display in the TSC is via the TV monitor and compbter te rmi nal. The TSC has direct access to as-built drawings of plant system and equipment, technical manuals, the FHSR, Emergency Plan
.tnd all plant procedures. The plant operating records are immediately available to the TSC via the plant records management system.
Additionally, in conjunction with an EPRI/NSAC demonstration program, Yankee Rowe is implementing a Safety Parameter Display System (SPDS) to be operational in the fourth quarter of this year.
Details on this system will be provided at a later date.
(5) Data transmission f rom Control Room to TSC is via the TV camera located overhead and in front of the Main Control Board, to the monitor in the TSC.
(6) All data displayed in the TSC is transmitted to the Emergency Operations Facility and Framingham office via the computer terminal data link described in Item 2 above.
We trust this information is satisfactory; however, if you desire additional information, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY G.
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J. A. Kay Senior Engineer - Licensing l
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Attachment A Descriptions of Emergency Response Facilities On-Site Technical Support Center a
An on-site Technical Support Center (TSC) has been establis,hed to direct
,the post-accident evaluation and assist in recovery operations of the plant.
The TSC is located adjacent to the Control Room and is habitable to the same degree as the Control Room for postulated accident conditions (see Figure 1).
A habitability study for the Control Room has been performed and was submitted in Reference (d).
2 The TSC has approximately 250 ft of floor space which is more than adequate for the people designated in the Emergency Plan that will respond to and inhabit the f acility under an emergency condition. A separate room (100 ft2) for the 3 NRC personnel has been designated as requested.
This center, established under the supervision of the TSC Coordinator and staffed by members of the TSC Organization shown in Figure 8.3, has the capability to display and monitor plant parameters (described in response to Item 2) needed to evaluate accident conditions. The TSC has access capability to the extensive Yankee computer network through ths NSD Engineering Support Center in Framingham, Massachusetts.
The center will accommodate sufficient plant technical staff needed to evaluate the plant condition. Communications with the Engineering Support Center in Framingham will reduce the necessity for a large number of additional technical support members beyond the three specialists from the Nuclear Services Division that will report to the TSC in the event of a Site Area or General Emergency. Upon activation, the TSC will provide the main communication link between the plant, Control Room, the NRC (red phone), and the Emergency Operations Facility. Details of this commun' cation capability are described in Section 7.0 of Reference (c).
The Technical Support Center has direct access to as-built drawings of plant sysems and equipment,
technical manuals, the FHSR, Emergency Plan and all plant procedures.
The TSC will be activated by the TSC Coordinator when a plant condition exists which requires on-going technical evaluation (i.e., Alert, Site Area or General Emergency Conditions). The TSC will have the capability to assess its radiological habitability. This assessment capability consists of monitoring for direct radiation and airborne particulates and sampling and analysis for ai rborne radiciodines. Appendix B of Reference (c) lists emergency equipment found in the Technical Support Center.
Additional emergency equipment is readily available in the storeroom located at the Health Physics Control Point should the additional supplies be requi red. The Technical Support Center will be deactivated by the Recovery Manager or the ISC Coordinator, depending upon the emergency class, when the plant conditions have stabilized such that continuous technical assessment is no longer required.
The Operations Support Center (OSC)
The Operations Support Center is located in the Control Room back foyer (see Figure 1).
It will be staff ed with sufficient in plant manpower needed to conduct protective and corrective actions in support of plant operations and is organized as shown in Figure 8.4 of Reference (c). An Operations Support Center Coordinator, appointed at the time of the accident, will direct the activities of this center. Should the OSC be activated, at least one person in each of the following areas of expertise will report to this center:
instrumentation and control, plant chemistry, health physics, electrical maintenance and mechanical maintenance. Off-Shift Control Room and auxiliary operators will report to this center. Communication capability at the OSC is provided by an in plant page/ intercom set.
Emergency equipment has been provided with additional back-up capability provided at the Health Physics Control Point. The OSC will be deactivated by the Recovery Manager or the TSC Coordinator, depending upon the accident class, when plant conditions have stabilized such that continuous operations support is no longer required.
Emergency Operations Facility / Recovery Center (EOF /RC)
As discussed in Reference (e) (see Attachment C), our upgraded emergency plan call for two Emergency Operations Facilities (F0F) - a near site location within a half mile and an alternate EOF about 12 miles from the plant efte.
Both EOF's are existing buildings. The near site primary EOF has been used as the emergency staging area since 1965 and is owned by Yankee Atomic. The alternate EOF is a facility in Buckland owned and normally manned by New England Power Company, a major utility owner of the Yankee plant.
The Furlon House, located on Monroe Hill Road, 2,500 feet southeast of the plant, is the primary Emergency Operations Facility / Recovery Center (EOF /RC). The overall responsibility for the functions performed in the EOF /RC belongs to the Recovery Manager. The Emergency Coordinator will be responsible for continued evaluation and coordination with of f-site authorities of all licensee activities related to an emergency having, or The Furlon House potentially having, environmental radiological consequences.
has sufficient assembly space and design to accommodate the emergency organization groups.
Both floors of the building provide approximately 2570 ft2 of floor space each. A separate office (130 f t2) has been l
designated for the 5 NRC personnel as requested.
The EOF, the main floor of the Furlon House, is shown in Figure 2 and maintains extensive communicatior.s capability with all other emergency Section 7.0 of Reference (c) details the extend of this capability.
cente rs.
Site entry control, radiological monitoring and decontamination activities l
will be coordina.ad f rom this location.
Copies of all emergency planning documents applicable to the f acility, l
, including area maps, emergency plans of the plant, states, and locals, emergencyimplementingprocedures,andtheplantFHSRaremaint}ainedhere.
l Extensive emergency equipment and supplies are maintained ut the EOF /RC This l
including the gear necessary to assess radiological habitability.
l consists of monitoring for direct radiation and sampling, and analysis for airborne radioparticulates and radioiodine. For a list of EOF /RC emergency l
equipment, see Appendix B of Reference (c).
The second floor of the Furlon House, also shown in Figure 2, will be utilized as a Recovery Center. The Recov 2ry Center is a centralized meeting location for key representatives f rom government agencies, industry organizations and plant management respcenible for limiting off-site consequences. The EOF will be a cential point for radiological assessment, the results of which will be provided to the off-site authorities for use in deciding about the need for protective actions.
g Reference (e) also provides the basis for our exception to "the guidelines
'cm near site EOF protection and ventifation isolation with HEPA filtration.
Alternate Emergency Operations Facility / Recovery Center In the event that the Furlon House becomes radiologically uninhabitable, an alternate EOF /RC has been established. It is located at the Shelburne Falls Lower Deerfield Headquarters of New England Power Company in Buckland approximately 12 miles from the plant. This alternate location will be utilized if the primary center becomes untenable at any time during the emergency. Emergency equipment similar to the primary EOF /RC will exist at the alternate, since Yankee Rowe maintains an emergency van stocked with emergency equipment in readily transportable containers. The transfer of the emergency response personnel f rom the primary EOF /RC to the alternate will be accomplished in stages to assure the important functions underway are continued as uninterrupted as possible. Under conditions which warrant activation of this center, a forward control point will be established for site entry control and a radiological dispatch area from an emergeacy vehicle stationed strategically near the site but outside the valley. Communication between the alternate EOF and the forward control point would be provided.
Emergency communications at alternate EOF are defined in Reference (c).
Engineering Support Center The Engineering Support Center is an area established at the Nuclear Services Divisions offices located in Fram'ngham, Massachusetts. This center will be activated for Alert, Site Area and General Emergencies. This facility maintains direct communications in addition to the computer terminal data link with the Yankee Rowe Technical Support Center and EOF /RC and has access to a complete set of as-built drawings and records pertaining to Yankee.
It maintains extensive computer capability which can be utilized to assess accident conditions at the plant. The Nuclear Services Division has the necessary technical ability and management expertise to perform a variety of emergency functions, such as engineering analysis, radiological evaluation, and plant system assessment, in support of the overall recovery eff orts.
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The Nuclear Services Division also maintains an Environmental Laboratory in Westboro, Massachusetts, which will provide 24-hour service in the event of
-3n emergency at Yankee Rowe. This lab provides capability for emergency environmental sample and personnel dosimetry analysis.
It will be managed by the Environmental Lab Manager or his designated alternate.
Media Center The Media Center will be located at the Oxbow Inn on the Mohawk Trail in Charlemont. This center will provide a centralized location for holding joint state, federal and licensee emergency news briefings in such a manner as
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not to hrsper on-going energency response. The Mzdia Center will be staff ed j
initially by the Public Information Representative and administration support personnel as required. Back-up support necessary for sustained operation will 1
be provided by the Yankee Project Manager and information personnel from New i
England utilities.
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l The Media Center will be equipped with appropriate communications and i
related equipment. This equipment will be readily available in the Shelburne Falls area and it will be brought to the Media Center when it lir activa.ted.
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FIGURE 2
Attachment _B Plant Parameters Transmitted to the TSC a
PARAMETER UNITS RANGE Loop 1 Hot Leg Temperature F
510-560 Loop 2 Hot Leg Temperature F
510-560 Loop 3 Hot Leg Temperature F
510-560 3
Loop 4 Hot Leg Temperature F
510-560 Loop 4 Cold Leg Temperature Wide Range F
70-600 Loop 3 Cold Leg Temperature Wide Range F
70-600 Loop 2 Cold Leg Temperature Wide Range F
70-600 Loop I Cold Leg Temperature Wide Range F
70-600 Maf r. Coolant Pressure PSI 0-3000 Subcooled Margin Monitor F
f; 0-700 Subcooled Margin Monitor PSI f; 0-3000 j
Pressurizer Wide Range Level Inches20-370 Pressurizer Pressure PSI 0-3000 Vapor Container Pressure PSI 0-50 Low Pressure Surge Tank Pressure PSI 0-75 l
Low Pressure Surge Tank Level Inches 0-72
, Hot Leg Injection Flow Inches 0-200 f
" Low Pressure Safety Injection Header Pre ssure PSI 0-800~
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l High Pressure Safety Injection Header Pres sure PSI 0-1600
PARAMETER UNITS RANGE High Preocura Safety Injection Headar Flow GPM 0-700 I
6 Primary Vent Stack Iodine Monitor CPM 10-10 6
Primary Vent Stack Particulate Monitor CPM 10-10 Primary Vent Stack Gaseous Monitor CPM 10-10 Main System Coolant Leak Air Particulate 2 Monitor 1 CPM 10-106 Main System Coolant Leak Air Particulate Monitor 2 CPM 10-106 8
Radiation Monitor MR/hr
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S/G 1 Blowdown CPM 10-10 6
S/G 2 Blowdown CPM 10-10 6
S/G 3 Blowdown CPM 10-10 6
S/B 4 Blowdown CPM 10-10 6
Bleedline Monitor CPM 10-10 6
Test Tank Discharge CPM 10-10 S/G Pressure 4 PSI 0-1500 S/G Pressure 3 PSI 0-1500 S/G Pressure 2 PSI 0-1500 S/G Pressure 1 PSI 0-1500 Emergency Feedwater Flow 3 GPM 0-100 Emergency Feedwater Flow 4 GPM 0-100 S/G Wide Range Level 1 Feet 0-30 S/G Wide Range Level 2 Feet 0-30 S/G Wide Range Level 3 Feet 0-30 S_/G Wide Range Level 4 Feet 0-30 Emergency Feedwater Flow 1 GPM 0-100 Emergency Feedwater Flow 2 GPM 0-100 -
Vapor Container Drain Tank Level Inches 0-42 Demineralized Water TK-1 Feet 0-15 l -
Primary Water TK-39 Feet 0-32 i
Safety Injection Tank Level Feet 0-38
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ATTACIDIENT C YAEC Letter to US!aC dated April 10, 1981 "TMI Action Plan Item III.A.I.2" i
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April 10, 1951 United States Nuclear Regulatory Coni ssion k'ashingt on, D. C.
20555 Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing
References:
(a) License No. DPR-3 (Docket No. 50-29) 1951 (b) USNRC Generic Letter 80-10, dated Febt uary lu, (c) USNRC Generic Let t e r #17, dated March 5, 1981
" Realistic Er,ticates of the Consecuences of Nuclear (d)
Accidents," Levenson, M. and Rahn, F.,
EPRI Sub je c t :
TM1 Action Plan Ite: III.A.1.2
Dear Sir:
(b) provided clarification of TMI Action Plan Itec III.A.1.2 -
Reference Facilities, and requested confirration that the Upgrade Emergency Support This letter responds to this implementation dates indicated uauld be met.
and provides descriptions of the f unctional co:pliance to (1) the request e=ergency operations shift staffing and augmentation carability and (2) the This info: cation is provided below.
f acility requirement s.
A.
Shift Staffing and Augmentation Enclosure A pro. ides a description of our plans to cocply with the functional intant of the shift staffing requirements.
Our the experience in nuclear operations supports our conviction that staffing levels described in Enclosure A assure adequate coverage for pro =pt emergency plan i=plementation.
B.
Eme rgency Response Facilities The conceptual design information as requested will be provided by B provides a description of the Emergency
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m7 " T 2Q arrangement we intend to implement by the NRC rangement has been reviewed against ile that no additional modiTications to the DUPLICATE DOCUMENT "Y " "
Entire document previously entered into system under h[ k / Q /[h ANO No of pages:
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