ML20004D033
| ML20004D033 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/01/1981 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0696, RTR-NUREG-0737, RTR-NUREG-696, RTR-NUREG-737, TASK-3.A.1.2, TASK-TM TAC-45978, TAC-46049, TAC-46121, NUDOCS 8106080223 | |
| Download: ML20004D033 (15) | |
Text
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e e" SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6
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suun 95813; (916) 452-3211 June 1, 1981
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DIRECTOR OF NUCLEAR REACTOR REGULATION 1
ATTENTION DARRELL G EISENHUT DIRECTOR
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%ipge DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT N0 1 TMI ACTION PLAN - li:M III.A.1.2 Your letter of February 18, 1981, requested the subtittal of a conceptual design for emergency response facilities by June 1,1981. Your letter of March 5,1981, provided us a copy of NUREG-0696, " Functional Criteria for Emergency Response Facilities" for guidance in the design of these facilities.
As discussed in our letter of April 6,1981, we are providing a conceptual design at this time for interim facilities whk.h we expect to have opera-tional by October 1,1982.
The attachment to this letter provides an outline of the requirements and the design proposed by the District which should be adequate for your pre-implementation review.
In additio,1, we feel our emergency plan submittal of February 27, 1981 will be useful in your review, especially in the area of staffing requirements.
If we can provide any further information, please
- advise, ft.16.
v VJohn Mattimoe Assistant General Manager and Chief Engineer b
Attachment 3
//
8106 go $3 4 'l ELE 0!?!C SYSTEM 3 E R VI N 3 M33E THAN 600.000 !N THF HEART OF C Ali F O R N ! A
RANCHO SEC0 EMERGENCY RESPONSE FACILITIES - CONCEPTUAL DESIGN SUBMITTAL NUREG 0737 - Section III.A.1.2 Upgrade Emergency Support Facilities Position Each operating nuclear power plant shall maintain an onsite technical support center (TSC) separate from and in close proximity to the control room that has the capability to display and transmit plant status to those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident. The center shall be habitable to the same degree as the control room for postulated accident conditions. The licensee shall revise his emergancy plans as necessary to incorporate the role and location of the TSC. Records that pertain to the as-built conditions and layout of structures, systems, and ccmponents shall be readily available te personnel in the TSC.
An operational support center (OSC) shall be established separate from the control room and other emergency response facilities as a place where operations support personnel can assemble and report in an emergency situation to receive instructions from the operating staff. Communications shall be provided between the OSC, TSC, E0F, and control room.
An emergency operations facility (EOF) will be operated by the licensee for continued evaluation and coordination of all licensee activities related to an emergency having, or potentially having environmental consequences.
Implementa tion For operating reactors, the upgraded emergency response facilities conceptual design shall be submitted by June 1,1981. For operating license application, such design information should be provided in connection with the OL review process.
The upgraded facilities shall be operational by October 1,1982, for all facilities licensed prior to that date.
Type of Review A pre-implementation review of the conceptual design submittals will be performed.
l A post-implementation review will be performed for the October 1,1982 requirement.
Documentation Required Facility conceptual design description shall be provided by June 1,1981 including:
i l
l 1,
Task functions of the individuals required to report to the TSC and EOF upon activation and for each emergency class; and 2.
Description of the TSC instrumentation, instrument quality, instrument accuracy and reliability.
3.
Description of TSC power supply systems, power supply quality, reliability and availability, and consequences of power supply interruption.
4.
Description of the design of the TSC data display systems, plant records and data available and record management systems.
5.
Description of the data transmission system to be installed between the TSC and control room.
6.
Description of data to be provided to the E0F.
h
. Discussion of Technical Support Center The TSC is an onsite facility located close to the control room (refer to drawing M-300 for location) that shall provide plant management and technical support to the reactor operating personnel located in the control room during emergency conditions.
It shall have technical data display and plant records available to assist in the detailed analysis and diagnosis of abnormal plant conditions and any significant release of radioactivity to the environment.
The TSC shall be the primary communications center for the plant during an emergency. A senior official, designated by the licensee, shall use the resources of the TSC to assist the control room operators by handling the administrative items, technical evaluations, and contact with offsite activities, relieving them of these functior.3. The TSC facilities may also be used for performing normal functions, such as shif t technical supervisor, training, and plant operators /
maintenance analysis functions, as well as for emergencies.
Technical Support Center Task Function Description The TSC equipment, or work stations, will be as shown on Figure 1.
The TSC will contain seven work stations having the following duties and functions:
Emergency Coordinator Tasks:
1.
Determine overall status of the emergency situation.
2.
Monitor all operational decisions involving the safety of the plant and its personnel.
3.
Approve all recommendations regarding the general public during an emergency situation.
4 Implement emergency procedures and (after conferring with shift supervisor) activate emergency organization necessary.
5.
Notify and inform offsite officials of pertinent facts and developments.
l l
6.
Receive assistance from record / documentation coordinator in assuring compliance with applicable regulations and procedures.
7.
Accept / initiate extra plant comunications via the communicator.
i Technical Support Center Coordinator Tasks:
1.
Assess current plant status.
2.
Develop recommendations and procedures for plant operations.
3.
Direct the efforts of his staff (Fault Analysis, Termination Recovery) in j
isolating the accident cause and determining appropriate core cooling measures.
l
. 4.
Make operating recommendations to the Operations Coordinator (or shift supervisor) in the control room.
5.
Keep the Emergency Coordinator appraised of his staff's efforts.
6.
Receive periodic updates from the Er.vironmental Threat Assessment team regarding the radiological /meteoroiogical conditions.
7.
Determine analysis paramaters, sampling rates, alarm points, etc.
(handled prior to and during the problem; data acquisition subsystem.)
Cocmunicator Tasks:
1.
Serve as liaison between the Emergency Coordinator and the other emergency centers.
2.
Maintain lo'gs and records of all outside communications.
3.
Serve as liaison between the Emergency Coordinator and state and local government, news service, and NRC.
Records / Documents Coordinator Tasks:
1.
Provide assistance to the Emergency Coordinator in assuring compliance with applicable regulations and procedures related to the emergency.
2.
Ensure that written documentatio. is maintained concerning: Communications; major plant status changes; operator actions.
3.
Ensure that a complete up-to-date set of plant documentation is stored in the TSC, e.g., Emergency Procedures, FSAR's, station manuals, technical specifications, Plant Operating Procedures, P&ID's, etc.
4.
Provide copus of any portion of the above documentation upon request of the TSC Coordinator or Emergency Coordinator.
1 Environemtnal Threat Analyst Tasks:
1.
Perform radiological assessment.
2.
Develop radiological monitoring plans and criteria.
3.
Keep TSC Coordinator and Emergency Coordinator informed of the radiological environment.
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4 May instruct the onsite Operations Coordinator to dispatch radiological monitoring teams that will report directly back to him.
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5.
Assess meteorological impact of radioactive release.
6.
Assess population danger.
7.
Make recommendations to Energency Coordinator.
8.
Provide support to the other analytical teams as directed by the TSC Coordinator.
. Fault Analyst Tasks:
1.
Assess current plant status during emergency.
2.
Localize fault to primary ce secondary system.
3.
Localize fault to the system level.
4.
Localize fault to the component level.
5.
Periodically advise the control room via the TSC Coordinator of recommended operations.
6.
Provide any engineering or technical support requested by. the control room via the TSC Coordinator.
7.
Provide support to the other analytical teams as directed by the TSC Coordinator.
Accident Termination / Recovery Tasks:
1.
Access accident severity with regards to ability to cool the core.
2.
Determine appropriate cooldown method.
3.
Reconnend cooldown method to control room via TSC or Emergency Coordinator.
4.
Monitor cooldown to assure proper core cooling progress.
5.
Modify / update recommendations as needed.
6.
Provide technical engineering support to the control room as requested.
7.
Provide support to the other analytical teams as directed by the TSC l
Coordinator, i
The tasks functions for each work station discussed above will be available, at all times, to the technical support center from an integrated computer system j
monitoring the plant.
l A discussion of the data display and information organization will be presented.
This following discussion indicates the selected design variables and provides the reason behind their selection.
(
Information Organization Individual CRT displays at a single viewing, provide the operator with a small subset of the total information availabic. Because of this, it is extremely important to structure the displayed information so that one can have ready access to that information which is required for the task.
Organization by level of detail is the most widely used structurinc seems ideally suitsd to the~ analytical functions. At the highest 1 detailed) summary information about the general status of critical can be displayed. The next lower level would provide information a cular system while at a lower level specific information about comp be available.
In addition to limiting the amount of information that the operator to a tend to, this hierarchial structuring approach provides him wi to focus on diagnosis of the problem at hand and identification of corrective action.
For these reasons the organization by level of detail approach will ever possible throughout the display development process of the TSC design.
The TSC conceptual designs for Rancho Seco have selected the format a display mode by mode basis, using that style which most appropria the information according to the operator information needs of the For example, a mimic format was chosen for system level information this allows the operator to obtain an overall view of the system an relationship of elements therein. On the other hand, simultaneousi graphs are used when parameter trending is desired since this allow and precise identification of parameter interactions over time.
Blink coding will be used to gain operator attention. Blinking deg and is therefore not recommended for alpharumerics whose value must fore, in the TSC displays, blink coding will only be used for param radiation monitors in alarm.
Technical Support Center Console Design:
A preliminary task loading analysis revealed the need for duel CRT I
operator console in order to accommodate situations where simultane page access is necessary. Duel 19 inch CRTs were determined to be to accommodate the proposed display pages and were therefore utiliz.
console design for the final TSC display system.
Due to the long range computer study and the need for an integrated to meet the requirements set forth in NUREG-0696, SMUD will not be,
a fully redundant and integrated system by the required October 1, Therefore, we will only be able to provide a TSC with five single Cl j
A conceptual block diagram of this system is provided by Figure 2.
to Figure 2 and to support our position in regards to the integra.tet l
Figure 3, the schedule for procurement and implementation of the fir l
The single CRT stations will be operational, with existing plant da-
[
Rancho Seco plant process and back-up computer system.
Description of TSC Instrumentation:
The instrumentation for the TSC was mentioned in the previous sectic to the October 1,1982 conceptual design. As stated in our April 6 in resconse to your February 18, 1981 letter, SMUD cannot follow a lation sequence if required to implement those requirements as set -
latory Guide 1.97 for an operational emergency response facility sy:
l October 1, 1982 date. However, every effort will be made to provide as addressed in Regulatory Guide 1.97 for the proposed interim syste possibility Joes exist for the signals as required, they will not mc l
criteria as specified by Regulatory Guide 1.97.
The process sensing devices presently installed at Rancho Seco all were procured to have an accuracy of t 0.05% of full scale and have been operating in our systems for approximately 8 years. Therefore, the accuracy and reliability should be acceptable for our intended interim system.
L.
Description of TSC Power Supply The power for the interim technical support center CRT display, line printer, and typewriter will be supplied from a battery backed inverter system, however, this power source will not be lE qualified. The devices within the TSC will be split between the F and J systems that exist within our present power distribution of 120 VAC.
The power for integrated system will be from a new diesel backed battery and inverter system. All of which will be qualified lE. The distribution to the TSC will be in such a manner that if power is lost, on one bus to any one console within the TSC, only one CRT on that console will be lost.
Description of Data Transmission All devices within the TSC; CRTs, printers, etc., will be directly connected to the computer system. Therefore, no transmission of data will originate from the control room.
Description of Data at Emeroency Operations Facility The data available in the technical support center is also available for the emergency operations facility. This data will be transmitted via modems and telephone lines to the EOF, Description of Safety Parameter Display System The safety parameter display system (SPDS) provides a d'. splay of plant parameters from which the safety status of operation may be assessed in the control room, TSC, EOF. The primary function of the SPDS is to help operating personnel in the control room make quick assessments of plant safety st3tus. Duplication of the SPDS displays in the TSC and E0F will improve the exchar.ge of information between the facilities and the control room and assist corporate and plant management in
+
the decision-making process. The SPDS shall be operated during normal cperation 4
and during all classes of emergencies. The SPDS should have the flexibility to i
allow future modifications to be incorporated such as the capability to handle operator interaction and diagnostic analysis.
The primary display may be individual plant parameters or may be composed of a number of parameters or derived variables giving an overall system status. The basis for the selection of the minimum set of parameters in the primary display shall be documented as part of the design. Table 1 is a listing of the parameters being proposed for the SPDS function. This table, at this time, is not final in its configuration i.e., it may increase or decrease in the number of monitored variables as the design is finalized.
SMUD has elected to provide a stand-alone seismically qualified micro-processor system for the control room function of the SPDS. This system, for the interim, will display the parameters as listed in Table 1 on a CRT located in the control room. The data and variables monitored by this system, if the capability exists, will be transmitted to the TSC and E0F via its own dedicated modems.
Until the final integrated computer system is implemented, the primary portion of the SPDS will consist of meters now installed in the control room. This configura-tion is a system that the plant operators are familiar with and have been using.
Power for the SPDS micro-processor will be taken from a vital power source-battery backed.
Isolation of any function associated with plant safety systems will be maintained throughout the SPDS implementation.
Integrated Computer System i
The intregrated computer that the Sacramento Municipal Utility District will be procuring and placing in operation in 1985, as shcwn on Figure 3, will have the basic configuration that is depicted by Figure 4 However, we do not intend to meet Section 7 of NUREG-0696 in its entirety.
For Example:
Section 7.1 Source of Technical Data states: " Parameters specified in Reg. Guide 1.97, Rev. 2, and Reg. Guide 1.23 shall be provided to the data acquisit'on system (LAS).
Isolation devices shall be required for all signal interfaces with safety systems to prevent interference, degradation, or damage to any element of the safety system as soe-ified in General Design Criterion 24,
" Separation of Protection and Control Systems", and IEEE-standard 279-1971, Section 4.7, " Control and Protection System Interaction". The signals may be provided at a control room interface or input connection to the process computer.
These inputs shall not be processed by a software-programmable device, or any device controlled indirectly by software, before entering the DAS except for data j
received in accordance with Reg. Guide 1.23".
l SMUD intends to meet the requirements set forth by Reg. Guide 1.97, in regards to l
isolating any signal being used for Safety Systems. However, the underlined state-ment above, "Section 7.1, Source of Technical Data", is too restrictive to be considered in the integrated computer system input system design. We intend to supply signals to the system from two differenet sources that are software controlled.
They ve; 1.
Temperature pressure saturation meter, that is a software controlled t
device, and 2.
The accident radiation monitoring system which will also be a soft-l ware controlled system. Both of the systems receive information from their sensors, process the data, via their own processor system and provide a channel output to l
the integrated computar system.
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Table 1 Safety Parameter Display Variables 1.
Reactivity Control
-6 a.
Neutron Flux 10 % to 100 power b.
Control Rod position In - not in c.
RCS boron concentration 0-6000 PPM d.
RCS Cold leg temperature 50*F - 620*F 2.
Reactor Core cooling i
a.
RCS hot leg temperature 50*F - 10*F 1
b.
RCS cold leg temperature see above c.
d.
Core exit temperature 50* - 2300*F f.
Degree subcooling 35*F-200*F sub to Super.
3.
Heat removal from primary System j
a.
Steam generator leve' to 30 ft.
b.
Steam generator pressure 0 - 1500 PSIG c.
Main feedwater flow 0 - 100%
d.
Auxiliary feedwater flow 0 - 100%
e.
High pressure injection 0 - 100%
f.
Decay heat flow 0 - 100%
g.
RCS hot leg temperature see above 4.
Reactor Coolant System integrity a.
RCS pressure see above b.
Ccutainment water level 0 - 8'
-.m,
-.,..,..-3 o-,-
. *+
c.
Containment pressure 0 to 180 PSIG d.
C6ntainment pressure 10 PSIA - 60 PSIG e.
Containment high radiation 1R - 107 R/hr.
f.
Pressurizer Code safeties Close - open g.
Pressurizer EMOV Close - open h.
Core flood tank level 0 - 100%
- i. Core flood tank pressure 1000 PSIG 1
5.
Radioactivity Control a.
Core exit temperature see above b.
RCS (gama Spectrum)
TID - 14844 source term 6.
Containment integrity a.
Containment isolation Closed - open b.
Containment pressure 10 PSIA - 180 PSIG c.
Containment H2 Concentration 0 - 10% or 0 - 30%
d.
Noble gas effluent discharge 10 102 u Ci/cc e.
Seismic (free field) design base f.
Containment High radiation 1R-10 R/hr.
7 g.
Aux building area radiation 10' - 103 uCf/CC i
7.
Supplemental (Public safety) a.
Meteorology L
Wind speed, direction, and i
temperature as required b.
Perimeter Radiation c.
Top of Containment rad monitor
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