ML20040F369
| ML20040F369 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/05/1982 |
| From: | Heider L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.A.1.2, TASK-TM FVY-82-10, GL-81-10, NUDOCS 8202090123 | |
| Download: ML20040F369 (6) | |
Text
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VERMONT YAN KEE NUCLEAR POWER CORPORATION 2
SEVENTY SEVEN GROVE STREET 2.C.2.1 RUTLAND. VERMONT 05701 REPLY TO:
ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGH AM, M ASSACH USETTS 01701 TELEPHONE 617 872-0100
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February 5,1982 4
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-1 United States Nuclear Regulatory Commission I' d r
Wa shington, D. C. 20555 L-
[11CJAttr @ tic 3n CIE O Attention:
Of fice of Nuclear Reactor Regulation Mr. D. G. Eisenhut, Director E
Division of Licensing 0,
b Re fe rence s :
(a) License No. DPR-28 (Docket No. 50-271)
(b) Letter, D. G. Eisenhut to All Licensees of Operating Plants and Holders of Construction Permits,
Subject:
" Post-TMI Requirements for Emergency Operations Facility (Generic Letter 81-10)," dated February 18, 1981 (c)
Letter, VYNPC to USNRC, FVY 81-93, dated June 12, 1981 (d) Le t t e r, VYNPC to USNRC, WVY 80-7, dated January 8,1980
Subject:
Additional Response to NUREG-0737, Item III.A.1.2
Dear Sir:
Reference (b) requested that a conceptual design description covering specific areas of the Emergency Support Facilities (ESP) be submitted by June 1, 1981.
Vermont Yankee submitted, in Reference (c), a partial response and committed to provide the remaining information in January, 1982.
Since that time, we have been involved in a substantial engineering ef fort to develop the information requested.
During this effort, we have been plagued by many uncertainties regarding regulatory requirements which, while not directly related to the design of the ESF, have a significant impact upon the type of equipment which should be used and the method of integrating this new equipment into the existing plant systems.
One fact has become increasingly clear as we have pursued our investigation: any permanent, long-term modifications to be made in plant instrumentation and display systems cannot be made in a piecemeal fashion.
Only a total integration of all aspects of this ef fort will suf fice to provide a truly ef fective, workable and stable design. These aspects include:
1)
Recent developments in computer / instrumentation technology.
2)
Evaluations of the desirability of a phased replacement of the present plant computer system.
O B202090123 820205' b'
PDR ADOCK 05000271 F
United States Nuclear Regulatory Commission Feb rua ry 5, 1982 Attention:
Mr. D. G. Eisenhut Page 2 3)
Impact of modifications on operating personnel and training requi rement s.
4)
Human factors considerations, including the assessment of information gained f rom control room design reviews.
5)
All applicable sources of NRC guidance.
For the reasons discussed above, and in light of our ongoing investigations in this area, we feel that it is appropriate at this time to provide conceptual information which describes some system aspcets as currently envisioned.
The items presented below are Vermont Yankee's responses to the documentation requirements of Reference (b).
1.
Task functions of the individuals required to report to the TSC (Technical Support Center) and EOF (Emergency Operations Facility) upon activation and for each emergency class.
This request was addressed in Reference (c), and no further response is required.
2.
Descriptions 'of TSC instrumentation, inst rument quality, instrument adcuracy, and reliability.
The instrumentation for all of the Emergency Support Facilities will be computer based. All parameters selected to display in any of the ESF will be input to a central processing unit or units.
Those signals which currently provide data to the Plant Computer System will be paralleled into the ESF Data System.
3.
Descriptions of TSC power supply systems, power supply quality, reliability and availability, and consequences of power supply int e r ru p t ion.
Power supply to the ESF Data System will be a computer grade uninterruptable power supply.
This will provide power of a quality sufficient to meet the needs of the computer sys*em.
Reliability and availability of the ESF Data System Power Supg ly will be suf ficient to support high overall system availabli'ty.
4.
Description of the design of the TSC data display systems, plant records and data available, and record management systems.
A data display system will be provided which will be engineered to pre sent the necessary information in a useful and readily uaderstandable manner.
Techniques utilized will be evaluated as being acceptable f rom a human factors standpoint.
The parameters which will be displayed in the TSC and the number of channels of each parameter are tabulated in Tables I and II.
Vermont Yankee has determined that these parameters are more than adequate for a sound, technical evaluation of plant status by the personnel who will be assigned to the TSC during all required conditions.
United States Nuclear Regulatory Comnission Feb rua ry 5, 1982 Attention:
Mr. D. G. Eisenhut Page 3 The plant records and data available in the TSC were described in Ref erence (c).
5.
Descriptions of the Data Transmission System to be installed between the TSC and Control Room.
The data which are supplied to the TSC will originate f rom the same process monitors which provide indication in the Fhin Control Room.
Communication between personnel at both locations will be provided.
6.
Description of data to be provided to the EOF.
This request was partially addressed in Reference (c).
In addition to the information previously presented, a list of data to be displayed on the EOF Data Display System is tabulated in Table III.
As previously stated, the information presented above is of necessity conceptual in nature. Vermont Yankee will provide a more detailed submittal containing schedular information when our evaluation of all aspects of the proposed system is complete. We believe that this delay in providing final design details is fully justified in light of the available facilities already described in Reference (d).
It should be noted that one aspect over which we have no control concerns the issuance of detailed, overlapping, and in some cases, conflicting NRC guidance. We are aware that the NRC is presently evaluating the role of guidance documents, such as NUREGs. We encourage such activity as a means of reducing the present uncertainties involved in designing required m:.d if ica t ion s, such as emergency support facilities.
We t rust this information adequately describes Vermont Yankee's position on NUREC-073 7, Item III. A. l. 2 at this time.
Should you have any questions, please contact us.
Very t ruly yours, i
l VERMONT YANKEE NUCLEAR POWER CORPORATION emd
- q l
L. H.
Heider Vice President LHH: RLS : dad
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-TABLE I
.TSCIS Variable Set - ( Analog)
PARAMETER /NO. OF CHANNELS RANGE APRM Power (6) 0-125%
SRM Countrate (4)
(-1) - (+6) log CRM IRM Percent Range (1) 0-100%
Rx Water Level (Uide Range CeMac) (1)
-200 - +200 in.
(Feedwater GeMac) '(1)'
127-187 in.
Rx Pressure (1) 0-1200 psig Control Rod Position (89) 0-48 Recire. Drive Flow A & B (4)-
0-41.815 KGPM CRD Flow (2) 0-70 GPM Feedwater Flow A & B (6)-
0-4 M lb/hr Steam Flow (1) 0-8 M lb/hr CST Volume (3) 0-512.4 KCal.
Torus Level (1) 0-3 ft.
RHR Rx Inlet / Outlet Temp. A & B (4) 0-30007 Drywell Pressure (2) 0-58.944 psia 0-120 in. Hg. abs.
D rywell-To rus Differential Pressure (1) 0-6.132 in Hg.
Torus Water Temp. (ave) (1) 0-3000F Drywell Area Temps. (13) 0-3000F-Reactor Bldg. Atmospheric Differential Pressure (1)
(-2) - (+2) psid ARM's (5) 0-4 log ar/hr ARM (1)
(-1) - (+3) log mr/hr.
Stack Gas Flow Rate (1) 0-280,000 CFM Off Cas Flow (1) 0-70 SCFM Of f Gaa Activity (1)
MCI /SEC (millicuries /sec)
Stack Cas Activity (1)
MCI /SEC (millicuries /sec) l Rx Bldg. Ventilation Monitor (2) 0 1-103 mr/hr l
(north-south)
Refuel Floor High Rad. ARM (1) 0-6 log mr/hr Containment Rad. Monitor (2) 1-107 R/hr Containmentf Act'. Monitor (2)10-106 CPM (Gas & Particulate).
~
Wind Speed (upper / lower)'(2) 0-100 mph-Wind-Direction (2) 0-360o Upper / Lower delta T (2)
(-5) - (+15)
F Rx Temperature Recire. Loop Inlet DA & B 270-5700F
O TABLE II TSCIC Set (Digital)
PARAMETER /NO. OF CHANNELS Diesel Generator Breaker, Opcn-Close (2)
RHR Pump Motor Breaker, Open-Close (4)
RHR Service Water Pump Motor Brecker, Close-Open (4)
Core Spray Initiate Signal, Normal-Start (1)
Auto Blowdown Initiate Signal, Normal-Start (1)
RCIC Initiate Signal, Normal-Start (1)
IIPCI Initiate Signal, Normal-Start (1)
Stand by Gas Treatment System, Stop-Start. (2)
Main Steam Line High Radiation, Normal-Trip (4)
Scram Discharge IIcader High Level, Normal-liigh (4)
MSIV Not Open, Normal-Trip (4)
Primary Containment High Pressure, Normal-Trip (4)
High Reactor Pressure, Normal-Trip (4)
Reactor Low Water Level, Normal-Trip (4)
Neutron Monitoring System Trip, Normal-Trip (4)
APRM Flux High-High, Normal-liigh (6)
IRM Flux High-liig;i, Normal-High (6)
Main Steam Line High Flow, Normal-Trip (4)
SRV Discharge Pressure, Normal-Trip (4)
Scram Demand Signals, Normal-Trip (36)
Mode Switch Position, Yes-No (4)
TABLE III EOF Variable Set (Analog)
PARAMETER RANGE Stack Gas Flow Rate (1) 0-280,000 CFM Off Gas Flow (1) 0-70 SCFM Of f Gas Activity (1)
MCI /SEC (millicuries /second)
Stack Gas Activity (1)
MCI /SEC (millicuries /second)
Rx Bldg. Ventilation Monitor (2) 0.1-103 mr/hr (north-south)
Refuel Floor High Rad. ARM (1) 0-6 log mr/hr Containment Rad. Monitor (2) 1-107 R/hr Containment Act. Monitor (2)10-106 CPM (Gas & Particulate)
Wind Speed (upper / lower) (2) 0-100 mph Wind Direction (2) 0-360 Upper / Lower delta T (2)
(-5) - (+15)
F