Text

Forwards Public Version of Licensee Response to NRC Request for Addo Info Re Conceptual Design of Emergency Response Facilities Per NUREG-0696 & Generic Ltr 81-10
	ML20040F903
Person / Time
Site:	Prairie Island
Issue date:	01/26/1982
From:	Mayer L; NORTHERN STATES POWER CO.
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML20040F900	List: ML20040F903;
References
	RTR-NUREG-0696, RTR-NUREG-696 GL-81-10, NUDOCS 8202100451
	Download: ML20040F903 (35)
	v • d • e

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i Northem States Power Company 414 Nicollet Mall Minneapolis. Minnesota 55401 Telephone (612) 330 5500 January 26, 1982 W

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Director J

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US Nuclear Regulatory Commission Washington, DC 20555 raz xl-

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Prairie Island Nuclear Generating Plant 93 Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Emergency Response Facilities Generic Letter 81-10 Our letter of January 7,1982 pointed out that we were in the final stages of addressing the items of concern outlined in Mr R A Clark's letter of November 23, 1981 and that we would submit this information together with projected implementation dates by January 22, 1982. This supplemental information would further describe how we are meeting the functional requirements of NUREG-0696 (final report).

Attached is our response document which addresses each of the items of concern in the same format used in Mr Clark's November 23, 1981 letter.

In some cases our response information is supported by appendices and sketches.

We assume this additional information will remove the qualifications you placed on the acceptability of our conceptual design plan and therefore these items will not receive special attention during the proposed NRC post-implementation inspection. Unless advised to the contrary within the 40 day review period mentioned in Mr Clark's letter of November 23, 1981, we will continue with implementation of our conceptual design plan. Our proposed schedule for implementation is later than specified in your Generic Letter 81-10, but in reviewing all f actors we consider the dates l

realistic.

As discussed with your Project Manager on January 22, this letter has been delayed a few days due to severe weather af fecting the availability of our involved people, 7(ooS n o-Hoo oma L 0 Mayer, PE i

Manager of Nuclear Support Services no mn

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NSP RESPONSE TO ITEMS OF CONCERN IN NRC LETTER DATED NOVEMBER 23, 1981 I

-REGARDING THE PRAIRIE ISLAND EMERGENCY RESPONSE. FACILITIES E

i Specific Criteria Deviation

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1.

Technical Support Center Size The following additional justification is. offered to support b

the present technical support center size:

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As specified. in Appendix B of ou'r response dated June 8,

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1981, a maximum staffing of 20 individuals, including 5 NRC personnel, is expected in the technical support center - we believe that the present physical size of the technical support center is adequate to allow the functioning of the expected number of personnel.

B.

The full scale emergency plan drill conducted December 8, 1981 at Prairie Island did not reveal any deficiencies in the size of the technical support center even with up to six extra observers and controllers 'present in the center.

C.

The close-in location of the permanent EOF will allow close technical support of the plant staff if it becomes necessary to form a large technical support organization -

the permanent EOF is of sufficient size to support any spill-over from the technical support center.

D.

The present location of the technical support center is ideal for the function of control room support

.any imposi-tion of an arbitrary square foot per person criteria could result in forcing the relocation of the technical support center to a much less desirable location.

E.

The 75 square feet per person has never been adequately justified as a criteria - we feel that the number of people expected in the technical support center and the results of

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the drill conducted justify the present size.

I 2.

Dedicated communication between the control room, technical support center and the operational support centar.

A.

The plant telephone system provides one means of communica-tion between the 3 locations - the telephone system is powered from a non-interruptible inverter supply.

B.

A plant intercom system will be operational soon between these 3 locations - this intercom allows open-channel communication between these locations at 'ny time, and is not affected by any site phone system tra1Eic.

This system j

is also supplied by a non-interruptible poser system.

C.

The Operational Support Center is located directly adjacent through a single door from the Control Room - this provides for almost instant communication in case of any wire system /

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normal communication failures.

The location of the technical q

support center is directly across the turbine hall from 4,

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E! I 1l the control room and operational support center.

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j failure of the normal communication system.

j 3.

.The location of the back-up EOF ~55 miles from the plant.

j A.

The HQEC is the back-up EOF and is the corporate response i

center to nuclear plant emergencies.

This center will E

be functional during all emergencies in which the EOF is I

active. -Therefore this center will be fully functional at

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all times during an emergency and will be able to assume command of the company's emergency response personnel at any time the EOF should need to be evacuated.

Because of this center being in readiness it is the ideal location func-tionally for the back-up EOF.

We do not believe that the additional distance from the two nuclear plants is a sig-nificant enough detriment,to outweigh the obvious advantage this center has for being the back-up EOF, its obvious advantage being its complete functionability at 'all times.

B.

The HQEC/back-up EOF will have the capability to operate the plant dose assessment system remotely and also will have the ability to contact the field observing team.

C.

Appendix A describes the HQEC more fully.

Because of the above stated reasons it is not thought to be necessary to provide for individual back-up EOF's closer to the site.

We believe that to abandon the EOF and try to reinitiate a back-up EOF would lead to much confusion during the transition period.

It is felt that with the HQEC there will not be a problem with where the NSP command center for the emergency is in the extremely unlikely event that the EOF would have to be evacuated.

Information Inadequacies 1.

Functions of the TSC, OCS and the EOF.

Attached as Appendix A are functional descriptions of the Prairie Island emergency response facility.

These include the TSC, EOF, OSC, HQEC, backup EOF and control room.

2.

Location of the functional work area and work space arrangement for the technical support center and the EOF.

Attached as Appendix B are detailed arrangement drawings for the tech support center and the EOF Command center that con-ceptually detail the functional working areas and associated data and communication equipment.

Refer to our June 8, 1981 submittal for site location of these facilities.

Detailed enoineering has not been comp.'.eted for our permanent EOF Command center; therefore the Appendix B figure is a pre-liminary layout.

3.

Attached ar. Appendix C is a dimensioned layout of the O. S. C.

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The structural and habitability requirements for the EOF and

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RESPONSE

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Structure

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j The TSC Complex must be able to withstand the most adverse conditions reasonably expected during the design life of the plant including adequate capabili-ties for.(1) earthquakes, (2) high winds (other than

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tornadoes) and (3) floods.- The Prairie Island Facility complies with these requirements as follows:

Floods:

The technical support center is located on the operat-ing floor of the turbine building which is at elevation

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735'-0".

The high flood level for the plant is 70 3 '-6".

Thus the technical support center is not affected by flood conditions as per section 2.7 of FSAR (see figure 2.7-7, FSAR).

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Winds:

The technical support center is completely surrounded by the turbine building and hence does not experience wind forces.

The turbine building is designed for high I

winds of 100 mph as per Appendix B sections B.4.1 and B.6 (e) of the FSAR.

This wind speed exceed the re-l quirements of Uniform Building Code.

1 Earthauakes:

The design of the technical support center has been re-viewed for the earthquake loads specified in the Uniform Building Code, Zone I.

The review concluded that the reinforced concrete block wall and the prestressed concrete spancrete floor slabs will be able to with-stand earthquake forces.

The spancrete slabs are anchored to the block walls along column rows A and B with the reinforcement steel at 3'-4" center to center.

The slab rests on the block walls along the short sides of the technical support center.

The analysis of the short walls takes into o l

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2 consideration the friction between the walls and floors i

to transfer horizontal reaction forces due to earth-quake.

The forces are approximately 25 lbs/ft.

The design of the operating floor'at the turbine building.

I has been checked to verify that it will withstand addi-

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tional. dead loads, live loads and earthquake loads transferred by'the technical support center.

The load combinations and the allowable stresses for the floor I

are the same as those used for the original design and as specified in the FSAR.

2.

Habitability TSC personnel shall be protected from radiological

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hazards, including direct radiation and airborne radio-activity from inplant sources under accident conditions, to the same degree as control room personnel.

Appli-cable criteria are specified in General Design Cri-terion 19; Standard Review Plan 6.4; and NUREG-0737,

" Clarification of TMI Action Plan Requirements," Item II.B.2.

The habitability of the Prairie Island technical support center has been evaluated to determine the dose commit-ment to plant personnel occupying the TCS for the dura-tion of an accident.

The result of the analysis indi-cates that the post accident 30 day integrated TSC dose values are below the limits of General Design Criterion 19.

The whole body gamma and beta skin doses due to exposure to noble gas radionuclides, and the thyroid dose due to inhalation of iodine radioisotopes were evaluated on the basis of source, strength, atmospheric transport, and j

the TSC room protection including HVAC considerations.

l Dose commitments were evaluated for the following time intervals:

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0-8 hours 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months i

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1 Source terms were determined assuming Regulatory Guide

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1.4 guidance.

In the case of LOCA, 100% of noble gases and 25% of the iodines present in the reactor core are assumed to escape to the containment and are initially

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The sourc6 term for each iso-i tope of iodine, xenon, and Krypton is calculated in

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terms of curies released within each time interval, as g

l stated above.

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The skin dose, whole body dose and thyroid dose (with and without cont. spray) for different time i

periods are:

SKIN WHOLE THYROID DOSE DOSE BODY DOSE NO SPRAY WITH SPRAY TIME (REMS)

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0-8 HRS 12.00 0.45 11.56 0.50 l

8-24 HRS 2.36 0.04 5.48 0.11

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1-4 DAYS 2.41 0.03 4.33 0.09 4-30 DAYS 1.38 0.01 3.32 0.07 4

TOTAL 30 DAYS 18.15 0.53 24.69 0.77 In this analysis the post-accident 30-day integrated TSC dose valves are below the limit of GDC 19.

Accord-ing to this criteria, TSC should provide radiation pro-tection such that personnel occupying the room do not receive radiation exposure in excess of 5 rem whole body or its equivalent to any part of the body, for j

the duration of the accident.

Beta skin dose from air-j borne activity within the room and thyroid dose from i

the inhalation of radioactive iodine should not exceed i

30 rem separately.

TSC HVAC System The system consists of the following:

l4 An air handling unit comprised for a " draw through" 1.

fan having a rated capacity of 3,000 SCFM at a static head of 1.0 "W.C.",

a cooling coil with an i

air cooled condensing unit rated at 7 1/2 tons, an electric heater rated at 5 KS, and control dampers.

2.

A return fan having a rated capacity of 3,000 SCFM' at a static pressure of 1.0 "W.C.".

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An HVAC Clean-up Unit comprised of a prefilter, an 1

upstream HEPA filter, a downstream HEPA and a fan.

1 The fan will have a rating of 3,000 SCFM at af sta-tic pressure of 6.0 "W.C.".

This system operates to satisfy the heating, cooling, and pressurization requirements of.the TSC.

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i During normal operation, outside air is mixed with return

'i air through control dampers and is supplied to the RSC through an air handling unit which consists of a filter, 3,

a cooling coil (with an air cooled condensing unit), a y

heating coil, and a fan.

The air is returned ec the air handling unit through a return fan.

2 During emergency operation, the normal outside air inlet will be closed, the return fan will be shut.off and isolated, and the normal return damper will be fully open.

Air will be supplied to the air handling unit at the return air opening through an HVAC Clean-up Unit, which consists of a prefilter, an upstream HEPA filter, a carbon filter, a downstream HEPA, and a fan.

The air into the HVAC Cleanup Unit is a combination of outside air and return air such that the TSC will be under,a positive pressure.

The operation of the HVAC system is controlled from

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within the TSC.

When the TSC is activated the HVAC' system will be switched from the " Normal" mode to the

" Emergency" mode as discussed above.

l B.

EOF 1.

Structure l

The EOF Complex must be able to withstand the adverse conditions reasonably expected during the design life

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of the plant including adequate capabilities for high

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winds (other than tornadoes) and floods.

The Prairie Island EOF complies with these requirements as follows:

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Floods:

The ground floor elevation of the EOF is 699 '-0", which is 11 feet above record historical floods.

While the plant itself is designed for a maximum probable flood elevation of 703'-6", the EOF will be able to with-stand the reasonable expected flood (100 year).

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Winds:

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The entire building housing the EOF is designed as follows:

a.

The area where the EOF is located is surrounded with at least 8" precast concrete 5clid walls and 8"

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precast concrete solid roof slabs.

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b.

The remaining areas are surrounded with 12" precast i

concrete (hollow core) wall panels (consisting of 2" insulation and 10" concrete) and steel roof deck.

Additionally, the building has been designdd in accord-

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ance with the Uniform Building Code and is therefore c

designed to withstand the raasonable expected high winds.

2.

Habitability The habitability of the EOF has been evaluated to deter -

mine the dose committment to personnel occupying the EOF for the duration of an accident.

The results of the analysis indicates that the post accident 30 day inte-grated EOF doses are below the limits of General Design

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Criteria 19.

Regulatory Guide 1.4 was used to determine a'ctivity l'evels in the containment following a DBA-LOCA.

Activity releases are based on a containment leakage rate of 0.25% per day for the first day and 0.125% per day thereafter.

The EOF's minimum 8-inch concrete shielding provides a protection factor greater than 5.

(A 6-inch concrete shield is necessary for a pro-tection factor of 5.)

The ventilation system is designed to have outside air enter the shielded area, through HEPA filters (99.97% efficiency on 0.3 micron DOP particles) and then recirculate within the area.

The resultant Prairie Island doses calculate to be:

Doses In Rems Thyroid Whole Body Beta-Skin Total Doses 22.4 0.84*

4.45 GDC 19 Doses Limits 30 5

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5.

The radiological monitoring systems to be used in the TSC, the OSC and the EOP.

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TSC and EOF

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Radiation monitoring systems for these areas consist of

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either permanently installed and dedicated portable-type

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The following is a list of typical radiation j

monitoring equipment located in the TSC and EOF.

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1-VAMP - Victoreen Area Monitoring Portable - range 1.

j 1-1000 mr/hr, alarm (visual and audible) setpoint s

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15 mr/hr J

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1-RM-14 or equal with 2" pancake probe - range

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j 10-50,000 cpm 3.

1-RO-2A or PIC-6A range 1 mr/hr --1000 mr/hr 4.

1 - continuous air monitor (CAM) (particulate, gas (silver ze lite absorber) gange:

and iodine) 6 particulate = 10-10 cpm, iodine 10-10 cpm.

AlarmsIl0 (visual and audible) pagticulate:

3 x 10 c/cc iodine:

1 x 10 c/cc 5.

1-A.C. powered air sampler All instruments are calibrated semi-annual]v except for the CAM which is calibrated annually.

B.

The radiation monitoring system for the OSC is similar to that of the TSC except no CAM is provided in the OSC.

The following additional instruments are available in the OSC:

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2-RO-2A or equal survey meters 2.

1-Teletector survey instrument 3.

One battery powered air sampler (equipped with silver zeolite absorber cartridge) l I

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6.

The design, hardware, location, software and layout of the 4'

Phase II and Phase III data acquisition systems and their

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RESPONSE

PHASE II DOSE ASSESSMENT SYSTEM 4

i The technical description of the Dose Assessment System is

-J attached as Appendix D.

The contract for this system is in the j

process of being signed at this time.

Installation of the S

system is scheduled for late 1982 with initial operation i

scheduled for January 1, 1983, dependent on hardware and soft-

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ware availability.

NUREG 0654 references a " Class B" model for implementation.

In reviewing the state of available models at this time, we have concluded that an extended Class A model is all that can be justified at this time.

Therefore, we are not planning to pursue a " Class B" model for use at Prairie Island.

This conclusion was reached after conversations with model vendors, NRC personnel and attendance at an NRC-sponsored seminar.

We will be submitting our extended Class A model for review when we have a complete description of it.

i PHASE III ERF DATA ACQUISITION AND DISPLAY SYSTEM System

Description:

See attached Appendix E for a conceptual description and layout.

Schedule:

Because of the significance of placing new displays,. output devices, printer, plotters, etc. in the Control Room, the approach to implementation of this phase must be carefully planned.

Our plans, at this time, are to proceed with specify-ing and procuring a replacement plant process computer and EP./

computer that will have capabilities for supporting Control Room enhancements, including SPDS,-possible safety system status monitoring and annunciator enhancement features.

To adequately specify, engineer and testout such a system is a long term undertaking.

The formal NRC requirements for the overall Control Room review are undergoing final review at this time.

In anticipa-tion that the requirements for this review will not change significantly, we have initiated our Control Room review project.

The output of this review should provide final guidance for possible Control Room changes.

Because of the complexities and l

long lead hardware items which are required for the final imple-mentation, our schedule at this time for Phase III is preliminary.

Based on a system as described in Appendix E, our earliest imple-mentation date is December 31, 1983.

To help us determine if our Control Room contains any serious deficiencies, we cooperated with an EPRI-sponsored effort to have a review completed on the plant Control Room.

This review is completed at this time and we have received a preliminary report.

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As we had anticipated, there are no major concerns associated with

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the Prairie Island Control Room.

Because of the demonstrated J!

adequacy of the present Control Room layout and information display

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system, we feel that an orderly approach to Control Room modifica-q~

tions is the most reasonable approach rather than the imposition of an arbitrary deadline that could result in counter productive 4

unsafe Control Room modifications.

ke SPDS:

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Because the ERF computer system that implements SPDS will not be a qualified seismic system, 0696 asks thar loss of the system be addressed.

We intend to back-up the primary SPDS display with a manual method such as described to the staff at the November 19 meeting between the Safety Assessment Group and the NRC staff.

This manual method will be tested and documented as part of the development of the SPDS system and will be plant specifically qualified as part of our Control Room Review effort.

7.

The Control Room emergency functions and interfaces with the other emergency response facilities.

RESPONSE

See Appendix A Functional Description of Emergency Response Facilities for a description of the role of the Control Room in the emergency plan.

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APPENDIX A FUNCTIONAL DESCRIPTION OF EMERGENCY RESPONSE FACILITIES fjf 14 3

3w Headquarters Emergency Center (HQEC) /Backuo EOF g

M When an " Alert", " Site Area Emergency" or " General Emergency" condi-4

.. E tion is declared, the Headquarters Emergency Cen'ter (HQEC) will be' (f

4 activated at the NSP Corporate Office.

The purpose of the HQEC is 4

to provide a command and control center to coordinate the activities

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of NSP departments and personnel providing support for the affected

'T plant and the EOF.

The HQEC will be staffed by a small number of 1

personnel designated to provide interfaces between the various departments within the NSP General Office, the organizations at the 4

EOF and the affected plant, NSP regional organizations and outside agencies.

The HQEC is located in Conference Room 8A/B in the General Office and provides a convenient location to control,the activities of the various departments.

The HQEC is not intended to function as a work space for the various cepartments.

The key departments may have representatives located in the HQEC but the primary functions of each department assisting in the emergency response will be conducted at normally assigned work spaces.

Personnel functioning in the Power Production Management position, would norma'ly be stationed in the HQEC with a small staff to handle routine administrative functions.

Contact with key personnel in the NSP departments is provided by special centrex telephone lines in the HQEC.

Additionally, due to the proximity of the HQEC to departmental work centers, personal E

contact can be quickly arranged for conferences, discucsions or the s

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must provide.

The HQEC is supplied with the equipment necessary

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Office emergency activities.

Dedicated telephone and radio

.f communications have been installed to provide normal and backup k

meth'ods of communicating with the EOF and TSC.

A special mobile

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cabinet containing technical references, special telephones, and administrative supplies necessary for the HQEC command and control

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function has been established.

Additionally, status boards, site area maps, bulletin and chalk boards are located on the center's walls to provide a convenient means of displaying current infor-mation.

In the event the EOF is evacuated the HQEC has the ability to function as the backup EOF.

Nearsite Emergency Operations Facility (EOF)

The Emergency Operations Facility is activated during " Alert",

" Site Area Emergency" and " General Emergency" conditions.

The purpose of the EOF is to provide a command and control center for NSP offsite emergency activities concerned with identifying and limiting the consequences of the emergency conditions.

The EOF also serves as a work center.

The various support groups assigned to the EOF are provided with the necessary references, materials and equipment to effectively control the activities of the Corporate Emergency Response Organization.

Specifically, the following functions are coordinated at the EOF:-

Management of the overall NSP offsite emergency response to support plant activities Direction of offsite radiological survey teams Communications with State and Local government agencies e

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Consultation with NSSS Vendors, consulting firms i

I Consultation with the NRC and FEMA

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Recommendation of protective actions Review of public information releases 1

The EOF provides office space for each NSP group, key supervisors,

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State and local. officials, and the NRC, as well as a command' 4

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.J center.

Each space is provided with furnishings'necessary to perform routine office functions.

The NSP support" groups and governmental representatives will perform their respective ~

functions in these assigned offices.

The ccamand center is in-'

4 tended to function as a work space for the Emergency. Manager, Radiation Protection Support Group, and for'related critical communications.

These activities are assigned to this area due to the high volume of activity, and the importance of the infor-l l

mation handled.

Additionally, this area is the ce'ntral area for l.

displaying plant status, offsite survey status, conducting acci-dent assessment and directing the activities of the offsite

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Emergency Response Organization.

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The EOF is supplied with the equipment necessary to fulfill its f

function as the offsite response center.

Special telephone and radio communications links have been established with other response centers and mobile survey teams.

Back-up radio communi-cation is provided with the plant.

Radiation monitoring and decontamination equipment has been provided to rapidly supply offsite monitoring teams.

Office equipment such as facsimile machines, copy machines, microfiche readers and typewriters are provided to facilitate administrative duties and technical 9

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Eeneral office supplies are stocked in adequate j

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numbers'.. Operating procedures detailing the methods to activate

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the'EOPr onduct routine administrative operations, surveys and accident assessment,' provide security and deactivate the Emergency Organization are d'eveloped and are available in the EOF.

Other

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available.to EOF personnel.

Technical Support Center (TSC)

The Technical Support Center is located in the engineering con-ference area of the plant administrative offices across the f

Turbine Building from Units 1 & 2 Control Room.

The Technical Support Center (TSC) will serve as a center outside

of the Conthol Room from which the plant management, technical, and engineering support personnel will:

(1)

Support the Control Room command and control functions (2)

Assess the plant status and potential offsite impact (3)

Coordinate emergency response actions The Technical Support Center will have the following capabilities:

(1)

Have work space for about twenty people.

(2)

Have shielding and ventilation cleanup system (PAC filter)

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to provide habitability under accident conditions, j

(3)

Has an emergency locker containing monitoring equipment (radiation and airborne), respiratory protection equipment and thyroid blocking agent tablets.

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Have communication channel to all onsite and offsite emergency t

response centera (primary and backup).

(5)

Have a complete set of as-built drawings and other records such as plant layout pictures available.

(6)

Have the capability to record and display the following:

1 (a)

Plant System Parameters (1)

Reactor Coolant System (2)

Secondary System (3)

ECCS System (4)

Containment (b)

In Plant Radiological Parameters (1)

Reactor, Coolant System (2)

Containment (3)

Effluent Treatment (4)

Release Paths (c)

Offsite Radiological Parameters (1)

Meteorology (2)

Offsite Radiation Levels The Technical Support Center shall be activated when an Alert, Site or General Emergency is declared or whenever it is deemed necessary by the Shift Supervisor or the Emergency Director.

The senior plant management person present will.be Coordi..ator of the Technical Support Center.

This individual shall be responsible for establishing and maintaining lines of communications between the Technical Support Center, the Operational Support Center and the O

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Control Room, and shall also be responsible for establishing the

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monitoring of direct radiation and airborne activity in the "1

Technical Support Center.

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If activation of the Technical Support Center occurs during

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s normal work hours, instructions to report to the TSC will be 7j s

received over the plant public address system.

All members of

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the Operations %dmmittee on site shall report to the TSC.

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If activation of the Technical Support Center occurs during the off duty hours, the Shift Supervisor or an individual

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designated by the Shift Supervisor shall contact all Operations Committee members by phone or Radio Alert system and request them to report to the Technical Support Center.

Operation Suppo,rt Center (OSC)

The Operational Support Center will provide a center to assemble the necessary Operators, Radiation Protection Specialist, Instru-ment and Control, Electrical, and Maintenance personnel to support the operations of the plant unddr emergency conditions without causing undue congestion in the main Control Room.

1 The Operational Support Center is located in the Plant Operating Records Rooms, immediately adjacent to the main Control Room.

1 The Operational Suppcrt Center will be activated when an Alert, Site or General Emegency is declared or whenever it is deemed i

necessary by the Shift Supervisor or the Emergency Director.

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The senior person in the OSC shall be Coordinator and shall be responsible for establishing and maintaining lines of communica-t I

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If activation of the OSC occurs during a normal working day, instructions to report to the OSC will be received over the plant public address system.

Any Operations shift personnel on site that are not assigned to normal shift duty shall report to the OSC immediately.

The following personnel will also report to

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the OSC if on site (Additional personnel will be contacted as l

necessary):

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Raintenance Supervisors (2)

Station Electrician

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Instrument and Control Supervisor and Coordinators (4)

Radiation Monitoring Team Members -

If activation of the Operational Support Center occurs during normal off duty hours, the Shift Supervisor or his designee shall contact the follcwing personnel to establish an initial compliment of support personnel to assist in the emergency (additional per-sonnel will be centacted as necessary):

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Instrumentation is stored in the emergency locker which provides

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taminants.

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Radiation shielding is provided by concrete wall construction of the room.

Av emergency locker located in the OSC contains all equipment nec9ssary for re-entry into the plant.

This includes but not limit ed to both waterproof and cloth coveralls, respiratory pro-tectica (Scott Air Paks), dosimeters, radiation detection metors, air samplers, decontamination and first aid equipment.

Communication equipment (radio, telephone and intercom) is avail-able for contacting designated sections of the emergency response organizations.

Control Room The Control Room shall be the initial onsite center of emergency control.

Control Room personnel must evaluate and effect control over the initial aspects of the emergency and initiate responses necessary for coping with the initial phases of an emergency until such time that the onsite emergency centers can be activated.

These activities shall include:

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visor, with direction from the management personnel located either in the Control Room or Technical Support Center.

e communication equipment is available in the Control Room for con-tacting all onsite and offsite emergency organizations and per-sonnel.

The Control Room contains the necessary instrumentation (process and radiological) to evaluate all plant conditions.

Habitability is maintained by shielding and the special ventilation system (PAC Filter), which is capable of operating in a cleanup or re-cycle mode.

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9 APPENDIX D SYSTEM SPECIFICATIONS For Prairie Island Radiation Dose Conoutation System-Revisial 1 1.0 PROJECT DESCRIPTION Due to existing and proposed regulations regarding radiation dose monitoring in and around Nuclear Power Generating Stations and the increasing requirements for computer aids in the plant radiation and chemistry labs, Northern States Power has determined it will purchase a new dedicated computer system to meet these needs.

It has also determined that because Health Physics personnel are transferred between NSP's (Monticello and Prairie Island) Nuclear Plants during emergency conditions, the same basic software system should be installed at both sites.

A review of existing hardware and software systems revealed that Prairie Island will require a complete hardware system, while Monticello will implement a new software package on an existing DEC-VAX 780. The Monticello system will require some additional peripheral hardware. The required hardware systems are illustrated in Figures #1 and #2.

2.0 GENERAL INFORMATION The radiation dose computation system is an atmospheric dispersion and radiological dose assessment system.

Its intended use is for data generation for reports required by 10CFR50 Appendix I, Nuclear 1

Regulatory Commission (NRC) Regulatory Guides 1.23 (1980), 1.21, and NUREG 0654 Appendix 2 (1980). It will be used during accidental release and normal release of radioactive materials into the environment to predict off-site radioactive dose rates and doses.

It will track, on a real time basis, the dispersion path of a l

radioactivve release. The system will be used to solve the equations, and display the predicted path of the relase.

The system will have the ability to record for future reference, on a real time basis, the instantaneous and accumulated radioactive doses and dose rates for the skin, thyroid and whole body. The system will be able to resolve the doses at any distance determined by the operator from the plant to a distance of at least 50 miles in any direction. Atmospheric dispersion (Chi /Q) information will be calculated and output to colored, Cathode Ray Tube (CRT) terminals for graphic display. Real time meteorological information will be continuously available for retrievel by the oper tor. The system will provide visual displays of all results in graphic and/or tabular form.

All displays produced on a CRT will be reproducible on a video copier for permanent records.

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3.0.4 Site Boundary Radiation Monitors. TLD's are currently in place at. both plant sites. These devices are generally installed in each sector (22-1/2 degrees) at the site boundary and at a distance of five miles. They are collected, replaced, and read each quarter. Following an accident they 2

can be collected and shipped to NSP's contract laboratory in i

Chicago for immediate (eight to twelve hours) reading.

.j The RC may require the use of direct read-out instrumentation f

at these TLD locations. Pressurized ion chambers (Figure 7) have been used to provide this capability in the past. Site boundary direct radiation would be continuously monitored by these instruments and displayed in the plant. The dose assessment system would scan the site boundary radiation monitor input data, average and store the data. Radiation measurements could be correlated with dose calculations made using the effluent monitor and meteorological instrument data.

3.0.5 Meteorological Tower Instrumentation. Each plant site is provided with meteorological towers. Wind speed, direction, and temperature difference instrumentation is located at

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approximately ten meters and at the elevation of the plant effluent point (140 feet and 100 meters at Monticello and 140 feet at Prairie Island).

In addition, temperature, humidity, and rainfall instruments are installed.

3.1.1 Meteorological Data. The system shall poll the primary and q

redundant meteorological tower instrument data inputs for

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measurements of wind direction, wind speed, vertical e

temperature differential (delta T), ambient temperature, dewpoint, and precipitation.

This data shall be used to calculata the general relative dispersion (Chi /Q) values, and the relative deposition (D/Q) values. The meteorological instrument inputs shall be polled at appropriate intervals and the values stored in memory.

The initial meteorological inputs will include two independent data sets from the primary tower and a data set from the backup tower.

Data Sets #1 and #2 will include wind speed at each elevation, air temperature at 10 meters, delta temperature between each elevation, wind direction at each elevation, dew point at 10 meters, and rain fall at ground level.

Data Set #3 will include wind speed and direction at one elevation.

A stability class shall be calculated for ea-h data set.

Data sets 1 and 2 shall have stability class calculated by both the delta temperature and variation in wind direction method.

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7 The system will produce on demand all reports required by 10CFR50 Appendix I, Regulatory Guide 1.23 (1980), Regulatory Guide 1.21 and NUREG 0654. These reports are to be output on hard copy via printer.

-The system will be used far preparing reports and archiving chemistry lab work by providing report-formats'on lab CRT's into which test results can be entered. Completed reports will be output on paper via printer. Historical test results will be available to produce trends on the CRT and video copier on operator demand. Test report formats and historical trending should be fully. programmable from the CRT terminal. -

3.0 SPECIFIC INPUT DESCRIPTION 3.0.1 System Input. The inputs to the Radiation Dose Computation system will be received over a parallel bit direct memory access (DMA) channel. Specific details for this channel are

'to be defined before award of contract. These inputs will include: meteorological data, plant effluent release data, field radiation data, plant iodine and particulate data, and plant counting lab data. Separate RS-232 input channels shall be provided to receive data from three existing Canberra e

i Multichannel Analysers and a whole body counter.

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3.0.2 Normal and' accident release points at the Monticello and Prairie Island Nuclear Generating Plants are listed in Tables 1 and 2.

Each of these points is currently equipped with a r

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continuous gross activity monitor of some type which responds p

to normal pl.4nt releases. In addition, multi-range high level monitors designed for monitoring accident releases will be z

installed.

y The gross activity monitor responds primarily to noble gas activity. Charcoal cartridges are installed for iodine monitoring and particulate filters are installed for y

particulate monitoring. A silica-jel sampler may be installed i

for tritium analysis. These devices are removed periodically, h

analyzed in the chemistry laboratory, and replaced with fresh L

devices. On-line monitoring for iodines, particulates, and tritium is generally impractical for normal plant releases.

Each of the continuous monitors (norm,al and high range) will l.

have an input to the dose assessment system processor.

3.0.3 Chemistry Laboratorv Spectrum Analyzer. The results of iodine, particulate, tritium,.and other analyses will be transmitted to the dose assessment system directly from the gamma spectrum analyzer in the plant's chemistry laboratory.

Both plants have similar systems based on a Canberra l

multi-channel analyzer system.

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This data shall.be archived in tabular form and a graphical i

display developed which will display the historictl, trend of each calculation for the previous 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the.end of each 60 minute period the values shall be

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averaged and stored for future reference on mag tape in accordance with NRC Regulatory Guide 1.23, Sept 1980, APX.

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3.1.2 Plant Effluent Release Data. Plant effluent release data shall be polled every 5 seconds and used in the dose calculations required by 10CFR50 Appendix I.

These inputs shall also be used for the accidental release dose rate calculations, and are listed in Tables 1, 2, and 3 of this specification.

3.1.3 Isotopic Analysis Data. Spectral analysis of radioactive

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isotopes such as iodine, and noble gases, provide the isotopic data supplied to the computer. This data shall be input by the technician on a keyboard to'be located in the counting lab or directly from automatic analyzers.

3.1.4 Field Radiation Data. Field radiation data will be collected by mobile lab facilities. This data will be communicated to Emergency Operations by voice link. Provisions shall be made to input this data into the system by keyboards in the TSC or EOF. Control of the model shall be possible at one location at a time only. Transfer of this control point to be determined.

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3.1.5 Plant Data. The keyboards in the TSC and EOF shall have the i

capability of inputing to the computer any parameter which is required by any calculation. Data from plant area radiation monitors will be provided as real time inputs through the DMA channel.

4.0 SYSTEM COMPUTATIONS AND REPORTS 4.1.0 Airborne Effluent Calculations. Gross activity (and flow rate in some cases) for all normal and potential release points will be continuously scanned, averaged, and stored.

Isotopic analysis data from the last grab sample will be used for routine releases to determine the release rate of individual l

noble gases. Up to 15 noble gases resulting from the fission process, plus Ar-41, will be considered.

For accidental releases, until a grab sample can be analyzed in the chemistry laboratory, a predetermined noble gas mixture will be assumed.

Iodine, particulate, tritium, and possibly carbon-14 release data will be obtained from sample analysis and transmitted to l

the dose assessment system directly from the gamma spectrum analyzer or manually from a terminal keyboard.

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,7 Other equipment which may be required.by the NRC, or which we -

- i may choose to install, include on-line spectrum analyzers and c

iodine samplers at selected release points.

,1 The dose assessment system will scan both the normal effluent j

monitors and the high-range effluent monitors. When the

.3 normal monitors are off' scale, the high-range monitor will.be E

used in the release calculations, j

4.1.1 Airborne Dose Calculations. Results of the meteorological and effluent calculations will be used in conjunction with

' appropriate dose factors stored in the computer to determine dose rate at the site boundary and selected locations. Whole body, skin, and thyroid dose rate should be computed at 15-minute intervals.

In the case of emergency dose calculations, integrated dose should be available for the duration of the emergency.

Provision should be made to determine the dose consequences of a shift in wind speed or direction or magnitude of the release. These calculations would be initiated by terminal f

keyboard entries.

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Site boundary dose should be available for display on the control room CRT at the option of the operators.

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In the case of normal plant effluents, the quantities of each isotope should be integrated over each calendar month. Dose assessments at the site boundary and critical pathway should et '

be integrated over each month. Quantities released as well as c

doses should be summarized on a quarterly basis for use.in preparing the Semiannual Effluent Report for the NRC. Dose assessment models for accident and routine releases may differ to some extent (acute versus chronic exposure).

4.1.2 Liquid Effluent Calculation. Results of liquid release batch analysis will be directly input to the dose assessment system by the chemistry laboratory gamma spectrum analyzer. Other information concerning each release will be manually input from the terminal keyboard. Continuous liquid release points are equipped with compositing samplers. Composite samples are periodically analyzed in the same manner as batch release samples. Release quantities are integrated on a monthly basis.

4.1.3 Liquid Effluent Dose Calculations. Provision will be made for assessing dose resulting from normal plant liquid releases and accidental releases to the river.

Dose calculations will be based on manual and real time inputs to the dose assessment system. A model of river flow shall be provided based on river stage.

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Doses from routine plant releases will be integrated on a monthly and quarterly basis for use in preparing the Semiannual Effluent Report for the NRC.

i 4.1.4 Dispersion Factors. The system shall compute CHI /Q and D/Q t

.calculatins during normal plant operating condition as I

described in NRC Regulatory Guide 1.111 (1977).

g During a release of radioactive particles into the atmosphere the calculations used for the dispersion models shall be of the extended class'A model. The model shall be capable of handling variable wind fields in the horizontal plane. The model shall accept multiple inputs for wind speed and wind direction. These parameters shall be input to the system either by direct instrumentation or by keyboard entry at the operator's choice.

4.1.5 The system'shall run in three modes simultaneously. These modes shall be:

"Real Time", " Predictive", and " Simulation".

The " Predictive" ' mode shall accept initial conditions and selected future conditions such as release times and rates, wind speed and direction changes for specific clock times, by keyboard input. The model should then be able to run in accelerated time to display predicted plume behavior and dose rates.

a The " Simulation" mode shall accept input conditions from the plant training simulator via an RS-232 link. The supplier of 3

the RDA system shall specify the format and protocol for this NL link.

CRT displays shall clearly indicate the mode that is being displayed.

The plume shall appear as a graphical model overlayed on a map which shows the major land markings. The maps shall include all major roads, communities, and geological formations. The system shall be capable of dividing the maps into 16 sectors based on major compass points and indicating the population density for one mile intervals (Regulatory Guide 1.145 calculations).

J 4.1.6 Beta, Gamma and Thyroid. Whole body, skin, and thyroid inhalation doses chall be calculated for any specified f

location in any s:ctor up to a radius of 50 miles. These composite doses shall be resolved at 1 mile increments for the first 5 miles and 5 mile increments thereafter.

4 The total integrated dose for each sector of the emergency planning zone shall be calculated at 15 minute intervals.

t These doses shall be compared to predetermined alarm values JMN062681A07 1

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and annunciated if the actual dose er eeds the alarm limit.

Y These dose values shall be stored in bulk memory and used-to i

generate the semi-annual reports required by Regulatory Guide 1.21.

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4.1.7 Data Trends. The system shall be able to generate area maps on the CRT's.

Plume representations and isodose curves shall 5<

be displayed as overlays on the area map.

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Joint frequency tables of wind direction versus temperature

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differential of two heights (delta T) and wind speed versus delta T shall be output in the format required by Regulatory Guide 1.23 (1980).

The system shall display a trend plot of each input and each computed parameter. Each plot, chart, table and graph shall be updated every 15 seconds. Trending resolution shall be a

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minimum 512 dots vertically by 512 dots horizontally.

Each plot, chart, table, and graph shall be labeled with the Julian time and date and shall be able to be retrieved from memory by using the Julian time and date.

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Ifap displays shall be provided with radial distance from the i j plant of 2 miles, 5 miles, 10 miles, and 50 miles.

These maps shall display all roads, waterways, communities, and points of geographical interest.

7 All maps shall be divided into 16 radial sectors. Each sector shall be identified by a letter which represents the compass heading of the center line of.the sector.

A map shall be provided which shows the population count in each one mile radial increment of each sector.

Each map shall be able to be overlaid by the Plume Model or Isolpleth Model.

4.2.0 Reports. The reports to be generated shall be displayed as a list to simplify the selection by the operator. The report formats shall be specified before award of contract.

4.2.1 Chem Lab GeLi Analyzer, Whole Body Counter Reports.

(To be provided before Contract.)

4.2.2 Meteorology Report. The meteorology report shall summarize l

the joint f requency distributions of wind direction, wind speed, temperature differential and atmospheric stability.

NRC Regulatory Guide 1.23 (1980) and NUREG 0654 (1980) shall provide a basis for the report format.

(See paragraph 4.2.7.)

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1 4.2.3 Off-Site Radiation Dose Report. Shall be specified before award of contract.

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4.2.4 Dose Assessment Report. The dose assessment report format and ci,

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requirements shall be determined before award of contract.

q is 4.2.5 Effluent Report. The effluent and waste disposal report shall 1;

conform to the requirements found in the NRC Regulatory Guide

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1.21 (Revision 1 June 1974). Each report described in Reg.

2 Guide 1.21 shall be generated and output to CRT and printer, upon operator command.

l 4.2.6 Weather Advisorv Report. The system shall have the capability of automitcally interfacing a remote weather advisory service on a periodic basis and requesting a preform:*.ed report. This will be accomplished over a non-dedicated, hardwired telephone

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line at 1200 Baud. Auto call and auto answer is required.

4.2.7 Remote Analyzer Report. The telephone line discussed in 4.2.7 shall also be used to transmit data from a remote S-80 analyzer. The system shall auto answer, receive data and print the report.

4.2.8 Plant Area Radiation Monitor. Detailed graphic displays of each plant floor elevation shall show the radiation levels on a real time basis. Historical data shall be available in the form of hourly averages and maximums. This historical data shall be printed and dumped each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

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TABLE 1 MONTICELLO NUCLEAR GENERATING PLANT EFFLUENT RELEASE POINTS

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Type Effluent Location Flow Rate Remarks i

Air Plant Stack 4000 cfm 100 meter elevation j

.5 Continuous -gross monitor (scintillation detector) with iodine, particulate, and tritium sample holders Reactor building vent 280,000 cfm 140 foot elevation variable Continuous gross monitor (beta scintillator) with iodine, particulate, and tritium sample holders.

Turbine building and radwaste building exhaust air is released via the reactor building vent. There are no other airborne release points.

b Liquid Radwaste discharge 0 - 100 gpm Release via circulating pipe water discharge line or cooling tower blowdown line.

Manual Batch 0-1,000,000 Continuous gross monitor Gallons (scintillation detector) l 9

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Table 2 PRAIRIE ISLAND NUCLEAR GENERATING FI. ANT EFFLUENT RELEASE POINT I

3 Type Effluent Location Flow Rate Remarks g,

Air Unit No. 1 Shield 4600 cfm 185 foot elevation 2

Bldg (containment Monitors IR-12, IR-22 purges 1 & 2)

Z Unit No. 2 Shield 32,500cfm 185 foot elevation Bldg Monitors 2R-12, 2R-22 1

Unit No. 2 Aux Bldg 41,000 cfm 80 foot elevation (gas decay tank Monitors 2R-30, 2R-37 4

releases)

Radwaste Bldg 6,100 cfm 35 foot elevation Monitor R-35 I

Spent Fuel Area 18,000 cfm 80 foot elevation Monitors R-25, R-31 Main steam power

'.':r.io us 80 foot elevation

^

operated relief Monitor under valves (2/ unit) development Main steam safety Various 80 foot elevation valves (10/ unit)

Monitor under development Steam driven aux Various 80 foot elevation feedwater pump Monitor under steam vent (1/ unit) development Liquid Radwaste effluent 0 - 100 gpm Release to discharge canal Monitor R-18 Unit No. 1 Steam 0 - 60 gpm Option to release to Generator Blowdown discharge canal Monitor 1R-19 l

Unit No. 2 Steam 0 - 60 gpm Option to release to Generator Blowdown discharge canal Monitor 2R-19 Note: Air ejector vent for each unit will be routed to auxiliary building normal and special fan inlet. Releases will be monitored by auxiliary building or shield building monitoring system.

All release points except steam also provided with iodine, particulate, and tritium sample holders.

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Table 3 MONTICELLO NUCLEAR GENERATING PLANT METEOROLOGICAL INSTRUMENTS.

1 5

s Elevation Instrument Range Remarks Base level Rainfall 0.01 inch /tip Dewpoint

-40F to 100F j

10 meters Wind direction 0 - 540 DEG Wind speed 0.6 - 90 MPH Temperature

-40F to 100F Delta T

-7 to +7F 140 feet Same as 10 meters, except no temperature 100 meters Same as 10 meters, except no temperature BACK-UP TOWER Wind Direction 0-540 DEG Wind Speed 0-90 MPH 7

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Table 4-PRAIRIF. ISLAND NUCIIAR GENERATING PIANT METEOROLOGICAL INSTRUMENTS 5

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Elevation Instrument Range Remarks Base level Rainfall 0.01 inch /tip l

Dewpoint

-40F to 100F I,

40 feet Wind direction 0 - 540 DEG I

Wind speed 0.6-90 MPH Temperature

-40F to 100F Delta.T

-7 to +7F 140 feet Same as 40 feet, except no temperature BACK-UP T0kIR Wind Direction 0-540 DEG Wind Speed 0-90 MPH e

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System Sp:cific tien3 If R:visita 1 j

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5 5.0 SOFTWARE SYSTEM i

5.1 Operator Interaction A key lock shall be provided to separate the oper4 tor function i

and the programmer function of the system. The programmer shall J

be able to edit and modify any existing or future software in s

the system, as well as delete or add programs to the system.

?

The system shall be able to accept and operate on any input data

't substitution supplied from any key lock equiped keyboard. Any program using substitute data shall indicate the substitution on any printout or display of program results.

Provision shall be made in the software which allows-the programmer to assign an alpha-numeric point name (I.D. number) to each analog and digital input point. The system shall display the current value of any input point upon the operator's request.

5.1.1 Edit Constants and Calculated Values. The programmer shall be'able to enter and change any constants and calculated values used in calculating CHI /Q, signa-theta, and all dose, plume and iostopic models.

5.1.2 Edit CRT Display. The display on the CRT shall be used as an interactive device. A light pen may be furnished with the CRT in order to place the cursor at any desire position.

A CRT call up routine uhich displays a function menu shall be provided.

o 5.2 Software Requirements. Flexibility to change system software and add new programs to meet future needs shall be provided.

Future software may include, but not be limited to the model B predictive calculations required in NRC NUREG 0654 (1980).

The system shall operate so that under emergency conditions, there shall be no less than 30% free time with all the queues empty.

The Contractor shall supply all programming functions required including standard, software packages such as executive routine, interrupts, DMA control, output control, log formats, compilers, and assemblers. The Contractor shall supply all standard formulations required such as thermodynamic properties, thermocouple linearization, resistance temperature detector curves, etc. The Contractor shall supply all special formulations required for dispersion modeling.

All software shall become the property of Northern State Power.

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5 The software system shall provide the following features:

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Quick start-up of computer operation f

Trouble-free operation Efficient use of central processing unit

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Effective debugging procedures Well defined and advantageous operator interface

'2 s :

5.2.1 Fortran Compiler. A compiler shall be furnished that is 3

ANSI Standard X3.9-1966 Fortran IV complete with the latest extensions. The compiler will be used for modifying and adding processing specifications for new and existing system inputs and outputs, and for modifying the dispersion model.

I 5.2.2 Data Conversion. The system shall make all engineering unit conversions, and shall check all input values for reasonableness. Upon detection, faulty input signals shall be alarmed and all calculations using this value shall be flagged. Where possible, a transfer to redundant signals should be accomplished and alarmed.

5.3 Documentation. This section describes the Dose Assessment Computer system documentation to be furnished by the Contractor.

Six complete. sets of all documentation shall be furnished to NSP.

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The requirements for documentation describe in this section

,{

apply equally to the following.

3 Manufacturer's standard programs Custom programs i

Software diagnostics Hardware diagnostics a

Special operating system software 5.3.1 Program Descriptions. All programs shall be described using both macro flow charts and verbal descriptions.

The verbal descriptions shall include the following:

2 Definitions Program descriptions Program limitations i

5.3.2 High Level Language. All programs shall be written and documented in the high level language of Fortran IV.

Deviations from this requirement must-be approved by NSP.

5.3.3 Assembly Language. All programs shall be documented in assembly level language. A copious quantity of notes and comments shall be included.

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5.3.4-Program Storage. All programs. shall be-stored-onr magnetic tape or floppy disc. The contractor shall provide clean source tapes for all programs. Three complete sets shall be furnished to NSP.

-3 4

5.3.5 Hardware Maintenance. Sufficient documentation shall be N

provided to assure efficient maintenance of all

.j Contractor-furnished hardware by NSP personnel. This documentation shall include point-to-point wiring diagrams and schematic diagrams of all electronic assemblies, supplemented with ccacise descriptions of the theory of operation of individual systems.

The Contractor shall furnish docur.1entation which will assist NSP personnel in assuring a short mean-time-to-repair in the event of a failure. This may be accotaplished by documenting problem symptoms along with possible repair solutions.

5.3.6 Pro'gramming Reference. Documentatio1 shall be supplied to assist NSP Perscnnel in software development and maintenance. This documentation shall include descriptions of all programming languages, editors and utilities supported by the Dose Assessment Computer, w

Programming documentations shall be included on two levels. One level will be used for training personnel who have a programming background, but are unfamiliar with the particular language. The other level shall be

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used for reference by personnel who are familiar with

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the language, but need concise in-depth information for assistance.

.4 System Troubleshooting Guide. Documentation shall be supplied to assist NSP personnel in analyzing system failure.

Documentation shall include, but not be limited to, procedures to follow after a system failure to isolate the error, locations of pertinent operating system parameters for automatic restarts and a list of errors that caused the failure.

5.5 System Operating Software Regeneration. The bidder shall state as a part of his Proposal the method of configuring new system software as may be required by the Company after installation of the equipment. The bidder should assume that this could be due to any of the following ' additions or modifications.

Additions to random access memory Additions to mass storage Additions to CRT graphics Additions to the data base Additions of standard computer peripherals JMN062681A07 I

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i 5.6 Computer Diagnostics. The provision shall be made to dump the

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contents of the RAM specified by the user in any of the following formats.

i Octal Hexadecimal j

Binary g

Source

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The system shall have the capability to convert from hexadecimal (octal) or decimal to hexadecimal (octal) at a specified binary l

point. It shall be capable of transferring data from one peripheral device to another.

The system shall be able to calculate cpu freetime, continuous running hours, mass memory read / writes and read / write retries.

The system shall be able to calculate for the programmer the existing available memory, on demand.

The capability to insert a breakpoint at a specified location which allows two modes of operations, shall be included. One mode shall store and print specified registers and memory locations allowing the computer to continue. The second mode shall halt the program to permit manual inspection of register and storage location contents.

The system diagnostics shall perform the following functions:

Modify memory locations and registers Perform masked memory search Execute a program selectively List debug commands and error messages Dump memory Add hexadecimal or octal numbers (as required by the machine)

Change debug input devices 1

The software debug programs shall provide a complete check of all software programs. General on-line checking shall also be performed. The following failure alarms shall be displayed on the programmer / operator CRT when directed.

4 Peripheral device failure Mass memory failure

i Parity error Program hangup Input failure Output failure Power supply failure Failures which do not shut down the computer shall be alarmed on the CRT's and outputed on the printers.

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b In event of a computer failure, the system shall write to bulk j

memory random access memory data required to analyze the t

failure.

4

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This data shall be stored on bulk memory for later error analysis and printout.

j 5.7 Automatic Restart. The system shall be capable of an automatic

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restart. The following data shall be saved during a system failure or shutdown for use following an automatic restart.

All calculated values 15 minute averages 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months total values Continuous running and periodic averages Vendor shall state how power and system failures are detected, and how shutdown and restart are accomplished.

5.8 System Acceptance. All software shall be complete at the time of the acceptance test at the factory. All program work shall be done at the vendor. site. Vendor support during site start-up

~

is required with associated costs per day.

Factory test procedure shall be reviewed by NSP for completeness and shall conform to the requirements listed.

6.0 SYSTEM EARDWARE r;

The Dose Assesstent System shall include hardware systems to support t

the specific needs for each plant.

All equipment furnished shall operate successfully meeting all warranties in environments from 32 degrees F. to 130 degrees F. and 10 to 90% relative humidity.

Vendor shall supply a list of recommended spare parts and an option for the purchase of these parts.

6.0.1 Prairie Island The hardware system at Prairie Island shall include:

A.

A dual processor CPU based on the DEC-VAX-750 system.

B.

Dual disc memory system C.

one magnetic tape storage unit D.

5 color graphic CRT's E.

4 Video copiers F.

1 - DEC LA-120 Printer In addition the following existing equipment shall be incorporated into the system.

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A.

4 - DEC-VT-100 CRT Terminals B.

2 - DEC-700 Series Printers (1200 Baud)

C.

3 - DEC-LA-120 Printers D.

2 - Canberra Model 80 Analyzers E.

1 - Whole Body Counter F.

1 - Spare Model 80 Analyzer di Provisions shall be made to support a minimum of three k

additional color graphics CRT's and Video Copiers located at remote (10 miles) sites not-yet determined.

Alternate proposals based on DEC-PDP 11/44 or SEL-32/77 equipment will be considered.

The CPU's shall be configured in such a way that the normal work load is split. Radiation dose assessment and 1.9X-I should be accomplished on one processor and the remaining functions on the second processor.

In the event of a failure either processor should be capable

. of assuming the total work load.

System availability shall be 99.8%.

Supplier shall state expected availability and supply supporting evidence to this claim. This evidence shall be in the form of test data, reports, etc.

2:

6.0.2 Monticello

7..

The hardware to be supplied to Monticello will be limited to the following items:

A.

Dise drive B.

Mag Tape Storage Unit C.

Color Graphic CRT D.

Video Copier E.

LA-120 Printers Factory test procedure shall be reviewed by NSP for completeness and shall conform to the requirements listed in paragraph 8.0.

6.1 Computer Room Components. The components located in the computer room shall include the CPU and programming equipment for loading, dumping, developing and modifying programs. The components shall include test facilities for trouble-shooting both software and hardware.

6.1.1 Central Processing Units. The central processing unit shall be a store <l program digital computer having memory capability, hardware multiply and divide, hardware floating point arithmetic and accessory hardware which_

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is. adequate to perform all of the functions as required.

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The CPU shall be solid state design on modular printed circuit boards. Chassis wired electronic assemblies shall not be used.

i The size of the solid state random access memory (RAM) shall be at least 32,000 words (16 bits / word). There shall be sufficient reserve to allow for 30 per cent f;

spare duty cycle with all the queues empty during emergency conditions.

All memory shall be mulitiported with one open port.

The mass memory shall be sized to meet the specified conditions with a reserve of 30 per cent.

It shall be a modular type system for ease of interchangeability.

~

The central processing unit shall shut down upon loss of power. The processor shall, as directed by the operator, either remain shut down or automatically restart upon restoration of power.

All data inputs to the central processor from external sources will be accomplished by'a parallel bit DMA channel, from an owner supplied multiplexing system.

Vendor shall supply a multiported RAM capable of accepting at least two external DMA channels.

6.1.2 Multi-plexing Equipment. The requirements shall be determined before award of contract.

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6.1.3 Cathode Ray Tube Systems. The cathode ray tube systems (CRT's) shall be " broadcast grade".

All CRT's shall be capable of displaying eight colors. The CRT's shall be the 19-inch diagonal dimension type. The CRT's shall be equipped with polarized glass filters to minimize glare 1

h from external lighting. All CRT's shall have the character formation of 80 characters per line, with 30 lines per display, the character font shall be a 7 x 9 dot matrix. Programmable CRT systems shall be used.

All CRT displays shall reside in CRT memory, and be independent of the master CPU. Active data points contained within the displays as well as new groups of displays will be down loaded from the CPU as required.

i The keyboards associated with the CRT's shall at minimum be 64-key. ASCII type, with a typewriter configuration.

i The system shall have the capacity to drive 5 CRT's located at distances up to 3000 feet and 3 CRT's located at extended distances.

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5 6.1.4 Printers and Recorders. The printers shall be Digital.- -

.I Equipment Corp. Model LA-120 or equivalent.

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6.1.5 Magnetic Tape. Magnetic tape systems shall be supplied

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with the system. All required interfacing shall be s

provided including a hardware error detection and

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correction scheme.

The magnetic tape systems shall operate' with a density of 1600 bits per inch on nine separate tracks. The recording modes shall be NRZI compatible and conform to the recommendations in NRC REG GUIDE 1.23-1980 Appendix A.

A controller shall be provided with each tape drive.

The magnetic tape shall be 1.5 mil, 1/2 inch wide and shall be IBM compatible.

Program entry shall be from magnetic tape. No cards or paper tape shall be used.

The contractor shall provide new, clean, high quality, source tapes for all programs.

6.1.6 Disc Storage. The system shall include a modular fixed head disc for program and data storage. The disc shall be of a multiport design to allow data retrieval by an j;._

external communications processor.

All of the input data shall be stored on the disc. The

'f disc shall maintain a continuous record of the

~

preceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The data shall be stored in a way which allows retrieval from the disc in the format

, prescribed in Appendix A and B of NRC REG GUIDE 1.23-1980. The system shall transfer this data to magne-ic tape at the end of each hour for permanent storage. This shall occur automatically, provided the correct tape is mounted on the tape drive and the tape is mounted in the correct position.

If these conditions

(

are not met the operator shall be informed and requested L

to intervene.

Each magnetic tape shall

.m. at a a header.apecifying the period of the data containe and a label identifying the plant name and unir > a er Prior to any retrieval or storage operation s 'a u 8.5

. h the magnetic tape, a verification shall pe pertvixed to insure that the i

correct tape is mounted.

s When a magnetic tape is detected " full", a message shall inform the operator. A message requesting the. mounting e

of a new magnetic tape shall be generated.

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A catalog shall be maintained in a disc buffer-to i

identify tape number and contents (time period, type of log, and contents similar to the headers of the logs i

stored therein). When this catalog disc buffer becomes 80% full and every hour thereafter, a message shall

[

request the mounting of a magnetic tape in order to i

transfer the catalog to the magnetic tape. Reserve disc Q

storage shall be provided to allow the oy,erator/jrogrammer

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76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months to dump the catalog file to magtetic tape.

The system shall permit the operator / programmer to retrieve the stored information. The system shall accept a request in the form of a start time, stop time and function type. The system shall then automatically display the requested data on the CRT, using "page forward" and "page backward" control'.

If the requested data has not been logged a message shall be generated to the user.

The retrieval functions shall be automatic, the only operator actions necessary shall be requesting the appropriate data and mounting the catalog tape and the log tape.

6.2 Monitoring Locations. The monitoring locations are designated by NSP to monitor nuclear plant functions. There could be as many as 10 separate locations which require a color graphics CRT and a line printer / plotter.

~:

The present designated areas for the placement of one CRT, one keyboard, and one video copier are the plant control room, x

Emergency Off-Site Facility (EOF), Technical Support Center

.c (TSC), the Headquarter Emergency Center (HQEC), and CRT's only, in the counting lab and the post accident lab.

6.3 Data Links. The data links between contractor furnished equipment, located in the plant, shall be defined by the contractor. The data link to the EOF shall be by Fibre-Optic j

methods.

l Data links to offsite locations shall subscribe to E.I.A l

Standard RS-232C.

6.4 System Power. The system shall operate on 120 volt single phase inverted AC plant power. The following is a list of possible factors which must be accomodated.

Inverter Distortion: 16%

l Inverter Transient Response: 3 cycles Inverter Regulation, line and load 11%

Inverter Frequency Regulation: 10.15% for line and load

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e Computer grounding requirements shall be presented to NSP. ia_

f conjunction with the bid by the contractor.

j 7.0 OPEPATOR DISPLAY The operator / programmer should be able to build bar charts and alter L

graphics. The response time to a keyboard entry shall not exceed 2 g

seconds. Capability to transfer any display to hard copy shall be provided.

~~f; The graphics display shall be able to produce at least a 3 variable graph.

(Two Y values for each X value.)

The information on the graphics and. charts shall be updated every.5 seconds.

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A NO. OF PAGES REASON O PAGE ILLEGIBLE.

D HARD COPY FILED AT. h CF j

OTHER _

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D BETTER COPi REQUESTED ON _

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4 APPENDIX E ERP Data Acquisition and Display System General Description

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% e Prairie Island Nuclear Generating Plant is presently equipped with

~~

a Westinglmuse Prodac 250 ocmputer. 'Ihis machine has reached the end of its useful life.

l In response to the need to replace the Prodac 250 and the need to im- ~~

i plement new requirements stated in NUFm 0654, NUBH3 0696 and other re-lated federal docunents, Northern States Power organized an engineering i

effort to review the present state of the art and to design and install a new ocmputer system for the plant.

% is engineering effort is presently underway and on schedule.

A result of this effort was to configure the system around f6ur basic conponents:

1 A stand alone muntiplexing system 4

i 2.

A radiation dose assessment conputer system 3.

An emergency response conputer system 4.

A plarit process conputer system A conceptual configuration is shown on the attached figure. We follow-ing is a brief description of each of the four ccuponents.

i-(.

1.

Multiplexina System

j It was decided that an effort nust be made to keep all conputer sys-l tems from beccnung overloaded during energency conditions. To accom-t I

plish this it was necessary to decentralize some of the computer func-tions. It was decided that all conputers must' be operating frcm exact-ly the same data base and that data acquisition should not occupy nere l.

than 1 or 2 percent of any CPU tine.

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A stand alone multiplexor is planned to be used which will connect-3 all plant data at a rate fast enougtt to ctrnply with the require-

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ment of the data system. Se multiplemr will forward each data J

point sinultaneously to each caouter requiring that data point, and store it directly in the caputer's mencry through the use of a ENA (Direct Memory Access) channel. Essent ially, no cmputer

{

CPU time is involved. A rwinrviant channel multiplexor will be used,

}

providing an availability in excess of 99.99%.

2.

A raeliation dose assessment emputer system has been studied, a specification written and 'the system is being purchased.

A copy of the technical section of the specification is included as Appendix D.

It was determined that this system would be configured in a dual-redundant CPU system of sufficient capability that NURB3 0654, APX I and other health physics functions could all be inplemented in this Irachine. A Dec-Vax 750 system with approximately 600 M7ftes of disc storage was selected.

A considerable ancunt of study was done to determine the nature of the meteorological problems that might exist at our river valley site. 'Ihis work is continuing. A real time nodified potential flow model*has been purchased and will be site specific. It is believed that this model represents the state of the art and will provide the best site resident model available.

A direct link with the plant sinulator will provide a training mode which will enable plant operators to utilize the dose assessment system in the sinulator while training. 'Ihis will enhance the re-lationship between control room, TSC and EOF.

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'Ihe Emergency Pesponse Caputer System study is in the final stages

(-

, of conpletion. 'Ihis system is planned to be configured in a fashion i

sintilar to the dose assessment system in that a dual CPU with 32

(.

bits architecture will be enployed to assure high availability.

3 a

i

'Ihis system will support the SPDS and other items required by NUREG 0696, and be sized to support other non-IE software which may re-

- ?

quire' verification, validation, and security which is nere difficult if located in a general purpose plant process:ccxtputer.

'Ihis system is non-IE and not seismic qualified. All required data transmission and display requirements to the 'ISC, EOF and plant con-trol room have been designed into the system and will be accouplished on high quality color CRr's.

Ccrmunication with the IDF is planned to be through fiber optic cables which will el.uninate DII disturbances.

Tnis system is planned to be duplicated in the simulator.for training purposes.

l Availability should be in excess of 99.5%.

4.

The plant process computer functions is planned to be implenented in a separate system utilizing data fran the ccrmon data base as described earlier.

i l

l All normal functions including data logging, nonitoring, alarming, data display, efficiency calculations, reactor core nonitoring, etc.

l will be executed in this hardware.

In addition to the nonral mn-trol rocm output, this system will also interface with the TSC pro-viding the personnel there with the total plant data base.

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ML20040F903

Contents

Text

RESPONSE

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Description:

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ML20040F903

Text

RESPONSE

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RESPONSE

Description:

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