ML20085L602

Responds to Recently Promulgated 10CFR50,App E,Section VI Which Establishes Emergency Response Data Sys.Implementation Plan & Schedule & Plant Attribute Library,Per Rev 1 to NUREG-1394 Encl

ML20085L602
Person / Time
Site:	Cook
Issue date:	10/28/1991
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1394 AEP:NRC:1163, NUDOCS 9111040270
Download: ML20085L602 (13)

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INDIANA MICHIGAN POWER AEP:NRC:ll63 10 CPR Part 50 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50 316 Licenso Nos. DPR-58 and DPR 74 EMERGE NY !E PONSE DATA SYSTEM (ERDS)

U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley october 28, 1991

Dear Dr. Murley:

This letter is in response to time recently promulgated rule contained in 10 CFR Part 50, Appendix E.Section VI, which establishes the Emergency Response Data System (ERDS). Specifically, the attachments provido our plan and schedule. Attaclanent 1 contains the implementation plan. Attachment 2 contains the ERDS schedule following the 11 stepa delineated in FUREC-1394, Revision 1.

Jteachment 3 contains our Plant Attribute Library (PA1.) as delineated in NUREG 1394 Revision 1.

Our ERDS' implementation plan vas discussed with a member of your staff on October 8, 1991, at the NRC Region III offices in Glen Ellyn, Illinois. We would like to confirm our plaos, as discussed in that riceting:

1. Our emergency implementing procedures will be revised to incorporate the ERDS_ functions once the system is operational.

2. We will have a configuration control program for the Emergency _ l<esponse Date System. _ The ERDS will _ be maintained according to this configuration control program and in <4ccordance with the final rulo. Our configuration control program will include prud stons to allow NRC to review proposed system modifications which could affect the data co.~ununication protocol in advance of these changes to ensure that t.he changes are compatible-with the ERDS, Jf I ji  ;

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Dr. 7- E. Murley - 2 AEP:NitC:1163

'3. Our spwific Data Point Library (DPL) is not complete at this time, due to new cot puter systerns being placed in service to be used to host FJtDS. Our "PL will be subraitted at a later ciata following 1..ata11ation of the Unit 2 Plant Process Computei, rhe DPL will be submitted prior to July 1,1992.

Unis document has been prepared following Corporate procedures that incorporare a reasonable set of controls. to ensure its accuracy and completenoss prior to s1 &nature by the undersigned.

Sincerely, MY E.-E. Fitzp t ick Vice President tjw Attachments cc: D. 11. Williams , J r.

A. A. Blind - B (dgman J. R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector Bridgman NFEM Section Chief.

J. Jolicoeur AEOD E

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ATTACIU4ENT 1 *10 AEP:NRC: 1163 ERDS IMPLEMENTATION PIAN s

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Attachment 1 ERDS IMPLEMENTATION PIAN

SUMMARY

The Donald C. Cook Nuclear Plant intends to meet the ERDS iuplementation date of February 13, 1993. In order to meet the requirements set forth in 10 CFR Part 50, Appendix E, Section VI, the following major items must be completed:

1. Installation of the Unit 2 Plant Process Computer (PPC).

2. Provide Radiation Monitoring System (RMS) data to the Unit 1 FPC, Unit 2 PPC, and the Simulator PPC.

3. Provide meteorological data (MIDAS) to the Unit 1 PPC, Unit 2 PPC, and the Simulatot PPC.

4 Provide additional process inputs as required by ERDS, currently not on the PPCs, to the Unit 1 PPC, Unft 2 PPC, and the Simulator PPC.

5, Install a Real time Data Repository (RDR) computer to host ERDS.

6. Send the ERDS data from the Unit 1 PPC ar.d Unit 2 PPC to

'the RDR computer, which will output the ERDS data to the NRC and Emergency Response Facilities.

The simulator will be connected to ERDS directly from its PPC. We plan to send ERDS information from the simulator to the NRC during emergency preparedness exercises using the Unit 2 ERDS transmission line.

The six work areas. listed above are to be completed under Step 7lof the schedule provided in Attachment'2.

Quarterly testing of the ERDS will be performed in accordance with 10 CFR Part 50, Appendix E, Section VI.

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ATTAClliiENT 2 TO AEP:NRC:1163 ERDS SCIIEDULE Q

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Project description

Title:

ERDS IMPLEMENTATION PLAN FOR THE DONALD C. COOK NUCLEAR PLANT Project start: 9-12-91 Project end: 2-12-93 (REQUIRED END DATE)

Description:

THIS PIAN CONTAINS THE STEPS REQUIRED TO INCORPORATE THE DONALD C. COOK NUCLEAR PLANT INTO THE CRDS AS PER NUREG-1394,REV. 1, APP. A i

Legend oeeee Act:.v:.ty 6 Milestone Locked activity Ceeee Leeee

===ee Act:.k'a:

Part tv on critical pai hllycompletedactIvity Completed act10ity A Original start date  ? Original end date

..... Discontinuous activity .....+ Baselined milestone GANTT CRART ERDS IMPLEMENTATION PLAN

, 1991- r 1992 , 1992 , 1M2 , 1992 ,

ERDS IMPLEMENT ATION PLAN Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan STEP 1 AEP RECE6VES QUESil0NNAIRE Il

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NRC NQTIFIES CONTRACTOR (NUS EI) 0F RECElPT . . .

STEP 2 AEP CONTACIED BY NUS-El ' *

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NUS El TO DISCUSS SURVET 00ESilCNNAIRE ITEMS a . .

STEP 3 ARRANGE / CONDUCT SITE SURVEY . . =

NUS TO Visif AEP PRIOR TO RETU"N OF DPL & PAL ..... + - .

STEP 4 NRC INSTAL L PHONE LINES G COOK PLANT + . . .

DI AL Up TELEPHONE LINES

• MC0 EMS ARE SUPPLIED ennununee. .

STEP 5 AEP RETURh5 Dei, AND PAL QUES 110NNAIRE DEFINE DATA POINT / PLANT ATTRIBUTE LIBRARY - - ...........

STEP 6 NUS-El DEVELOPS ,OFTWARE FCR NRC DPL + + . .

IF kEQUIRED: AEP SPECIFIC SOFTWARE Div. BY NUS 4 - - + . . ...............n...n STEP 7 AEP DEV/ INSTALL ERDS SOFTWARE / HARDWARE - ' '

UNIT 2 DEVELOP / INSTALL / SITE TCST - ..........n....n......on... .

UNIT 1 DEVELOP / INSTALL / SITE TEST - ......... n......n...................o............. . .

COMPLETE ERDS SOFTWARE & PROCEDURES '

STEP 8 PRELIMINARY SOFTWARE TESTS: AEP/NUS El + , .

AEP/NU$ El TEST DATA TRANSMISSICW & DEBUG * + * .un STEP 9 FORMAL FACTORY SITE TEST AT NUS-El ACCEPTANCE TESTS PER'ORMED AT NUS El - - +n UPON SUCCESSFUt Cm PLETION: MOVE TO PRCD. SYS. * * * * * * * '

STEP 10 FORMAL SITE TEST AEP ERDS SYS. WITH NWC 4 a TEST WITH PLANT PR00. SYS AND NRC OP. CENTER -

STEP 11 AEP ERDS IN PRG)UCTION (CHANGE CONTROL) - -

IMPLEMENT CHANGE CONTROL A 'JUARTERLY TESTS - * * * * **

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ATTACllMErlT 3 TO AEP:NRC:1163 Responses to NUREG - 1.394, Revision 1. Appendix 8 PLANT ATTRIhUTE LIBRARY (PAL) 8 E

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Attachment 3 to AEP:NRC:ll63 Page 1 PLANT ATTRIBUTE LIBRARY (PAL)

I. Contacts Note: Please provide name, title, mailing address, ard phone number.

A. Survey Coordinator (i.e., contact for later clarification of questionnaire ansvers):

Karl J. Toth American Electric Power Service corp.

1 Riverside Plaza Colwnbus , OH 43215 (614) 223 2038 Senior Scientist t Computer Cardware Specialist (s):

Dave W. Fitzcharles Cery Hagoniers American Electric Power Service Corp. Cook Nuclear Plant 1 Riverside Plaza 1 Cook Place Columbus, OH 43215 Bridgman, MI 49106 (614) 223 3494 (616) 465-5901 x1471 Engineer 1 Computer Analyst I C. System Coftware Specialist (s):

Dav_ 71tzcharles Gary Hageniers Amerit Electric Power Service Corp. Cook Nuclear Plant 1 Riverside Plaza 1 Cook Place Columbus, OH 43215 Bridgman, MI 49106 (614) 223-3494 (616) 465-5901 x1471 Engineer I Computer Analyst 1 D. Application-level Software Specialist (s):

Dave W. Fitzcharles Gary Hageniers American Electric Power Service Corp. Cook Nuclear Plant 1 Riverside Plaza 1 Cook Place Columbus, OH 43215 Bridgman, MI 49106 (614) 223 3494 (616) 465-5901 x1471 Engineer I Computer Analyst I

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l Attachment 3 to AEP:NRC:1163 Page 2 E. Telephone Systems Specialist (s):

Dave J. Stephan Dave B. Vhisenant American Electric Power Service Corp. Cook Nuclear Plant 1 Riverside Plaza 1 Cook Place Columbus, OH 42?15 Bridgman, MI 49106 (614) 223-3587 (616) 465-5901 x1541 Engineering Technologist I comm. Tech. I i

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. o Attachment 3 to AEP:NRC:1163 Page 3 III. Selection of Data Feeders A. How many data feeders are there (six maximum)?

Unit 1 - 1 Data Feeder Unit 2 - 1 Data Feeder Simulator - Same as Unit 2 Data Feeder (planned)

B. Identify the selected data feeder and provide the following for each:

(1) a short description of the categories os data points it will provide (e.g. met, rad, or plant data points, by unit) and (2) the rationale for selecting it if r.nother system can alao provide its categories of data points.

Only one data feeder per unit and it will provide all of the categories of data required.

C. Which data feeder is the site time determining feeder? This should be the feeder which is providing the majority of the data points.

Only one data feeder per unit.

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Attachment 3'to AEP:NRC:ll63 Page 4 IV. Data Feeder Information (Applicable to Unit 1, Unit 2/ Simulator data feeder)

Note: A new Section IV must be filled out for-each feeder system aslected.

General Questions

1. Identification of Data Feeder a, What is the name in local parlance given to this data feecer (e.g., Emergency Response Information System)? Please give >

both the acronym and the stords forming it.

Real-time Data Repository (RDR) b.

Is this the site time determining feeder?

Yes

c. How often will this feeder transmit an update net to the ERDS (in seconds)? .

60 seconds-2-. Hardware Software Environscnt

a. l Identify the asaufa:turer and model number of the data feeder hardwkre.

92C MICROVAX 4000 (anticipated, but may change)

b. Identify tts operating system.

L VMS Version-5.X l :-

c. What method of timekeeping is implemented on this feeder

. system (Daylight Savings, Standard. Greenwich)?

Daylight Savings Time

d. In what time zone is this feeder located?

L Eastern i

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Attachment'3 to AEP:NRC:1163 Page 5

3. Data Communication Details a, . Can.this data feeder provide synchronous serial data communications (RS-232 C) with full-modem control?

Yes

b. Vill this feeder transmit in ASCII or EBCDIC?

ASCII

c. Can this feader transmit at a serial baud rate of 2400 bps?

If not, at what baud rate can it transmit?

Yes

d. Does the. operating system support ION /IOFF flow controlf Yes

1. Are any problems foreseen with the NRC using ION /IOFF to control the transmission of. data?

No

e. If it is not feasible to reconfigure a serial port for the ERDS linkup (i.e., change the baud rate, phrity, etc.) .

pitase explain why.

Not applicable

f. Do any ports currently exist for the ERDS linkupf No

1. If-not, is it possible to add additional ports?

'Yes, by buying a new computer.

2. ~If yes, will the port be used. solely by the FRDS or shared with other non-emergency-time-useraf Civ,

-details.

The port will be usad solely by ERDS.

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l httachment 3 to AEP:NRC: 1163 Page 6 l

4. Data Feeder Physical Environment and Management

a. Where is the data feeder located in terms of the TSC, EOF, and control room?

It is planned to be in plant process computer room, which is above the control room,

b. Is the data feeder protected from loss of supply of electricity?

Yes, it is planned to be protected,

c. Is there a human operator for this da:a feeder?

No

1. If so, how many hours a day is the feeder attended?

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