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Provides Response to Generic Ltr 89-06, Task Action Plan Item I.D.2 - Spds. Certification Stating Plant Unit 1 SPDS Sys Meets Requirements of NUREG-0737,Suppl 1 & Plant Unit 2 SPDS Sys Will Be Modified to Meet NUREG-0737,Suppl 1 Encl
	ML18038A661
Person / Time
Site:	Nine Mile Point
Issue date:	07/11/1989
From:	Terry C; NIAGARA MOHAWK POWER CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	CON-IIT07-465A-91, CON-IIT07-465B-91, CON-IIT7-465-91A, CON-IIT7-465A-91, CON-IIT7-465B-91, RTR-NUREG-737 GL-89-06, GL-89-6, NMP1L-0419, NMP1L-419, NUREG-0737, NUREG-1455, NUREG-737, NUDOCS 8907180072
	Download: ML18038A661 (20)
	v • d • e

N V NIAGARA 0 MQNLWK NIAGARAMOHAWKPOWER CORPORATIONI301 PLAINFIELDROAD. SYRACUSE. N.Y. 13212ITELEPHONE (315) 474-1511 July ll, 1989 NHPl L 0419 U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C. 20555 Re:

Nine Hoyle Point Unit 1

Docket No. 50-220 DPR-63 Gentlemen:

Nine Nile Point Unit 2 Docket No. 50-il0 NPF-69 The purpose of this letter is to provide you our response to Generic Letter 89-06, "Task Action Plan Item I.D.2 - Safety Parameter D1splay System".

Generic Letter 89-06 was 1ssued by the Commission to all 11censees to obtain the implementation status of the Safety Parameter D1splay Systems (SPDS) as required by NUREG-0737, Supplement l.

Attached to Generic Letter 89-06 was NUREG-1342, "A Status Report Regarding Industry Implementation of Safety Parameter Display Systems".

NUREG-l342 describes methods used by some licensees/applicants to implement SPDS requirements in a manner found acceptable by the Staff.

Specifically, Generic Letter 89-06 requested each licensee to prov1de one of the following: l) Certification that the SPDS fully meets the requirements of NUREG-0737, Supplement l, taking 1nto account the informat1on provided in NUREG-1342;

2) Certification that the SPDS will be modified to fully meet the requ1rements of NUREG-0737, Supplement l, taking into account the 1nformat1on provided 1n NUREG-1342, and the modification 1mplementation schedule;

3) If a certification cannot be provided, the reasons for the finding and a discussion of the compensatory actions to be taken.

To meet the requ1rements of Generic Letter 89-06, Niagara Hohawk submits the enclosed certification which states the Nine Nile Point Unit l SPDS system meets the requ1rements of NUREG-0737, Supplement 1, (Category I) and the Nine W907-MOOR'~9071 I PDR 4DOCK 05000220 P

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U. S. Nuclear Regulatory Commission Attn:

Document Control Desk July 7, 1989 Page 2

Mile Point. Unit 2 (NMP2)

SPDS system will be modified to meet the requ1rements of NUREG-0737.

Supplement l (Category II).

A list of the required NMP2 modifi'cations/evaluations and the scheduled implementation dates is also included.

Very truly yours, NIAGARA HOHAHK P R

RPORATION C.

D. Terr Vice President Nuclear Engineering 5 Licensing JT/011 f 7489G xc:

Regional Administrator, Region I Hr.

R. A. Capra, D1rector Ms.

M. H. Slosson, Pro)ect Hanager Hr. H. A. Cook, Resident Inspector

'ecords Hanagement

l,

UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of

)

Niagara Hohawk Power Corporation

)

Nine Hile Point Nuclear Station

)

Unit l Docket No. 50-220 and Unit 2 Docket No. 50-410 CERT I F ICATI ON C.

D. Terry, being duly sworn, states that he is Vice President, Nuclear Engineering and Licensing of Niagara Hohawk Power Corporation, that he is authorized on the part of said Company to s1gn and file w1th the Nuclear Regulatory Commission this certification; and that the following statements/information attached hereto are accurate.

C.

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Vice President Nuclear Engineering and Licensing Subscribed and Sworn to Before me this ~~

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NNP1 Nine Hile Point Unit 1 (NHPl) Safety Parameter Display System (SPDS) meets the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342.

A brief discussion is provided-below to clarify NMPl's position on NUREG-1342 Items III.A.l/III.B.l.

NUREG-1342 Sections III.A.l/III.B,1require all SPDS-related information be physically displayed such that the information can be clearly read from the SPDS user's typical position.

In the past, the main SPDS terminal and the Emergency Operating Procedures (EOP's) were located at the same work location.

However, converting the EOP's from procedure to flow chart format has resulted in locating the EOP's away from the SPDS terminals.

The NHPC Operations and Computer Departments are tasked with evaluating means to rectify this situation.

NHP2

, The Nine Mile Point Unit 2 (NMP2) Safety Parameter Display System (SPDS) will be modified to meet the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342.

The implementation schedule for the modifications required to bring about compliance with NUREG-0737, Supplement 1, are provided on Attachment 1.

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ATTACHNENT 1 o

4 Descri tion 1)

Radioactivity control will be added to the SPDS displays.

This includes plant overview display (Level I) and additional detail (Level II) display.

All five required safety functions will then be displayed on the SPDS

/

Checklist Section 2.1.4, 2.2.9, 3.1, 3.3 Scheduled C~om letion By end of first refueling outage 2)

Drywell temperature wi 11 be added as a

containment integrity parameter 3)

The SPDS reactor water level parameter has displayed invalid/erroneous information or has been'n a false alarm condition greater than 5 percent of operation.

A work request (HR 162049) has been issued to troublshoot.

2.2.10, 2.2.7 4.7, 4.8 By end of first refueling outage By end of first refueling outage 4)

High and Low Level setpoints will be re-evaluated as part of the overall SPDS modification.

5)

Complete verification and validation (V5V) requirements (as identified in the pre-implementation audit) i.e. man-in-the-loop testing, collect and centrally locate all necessary VKV documentation, invalidation test

5. 10 4.5, 5.15 By end of first refueling outage.

By end of first refuel ing outage.

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ATTACHNENT 1 Descri tion 6)

The SPDS screens cannot be clearly read from the EOP flowcharts.

A Problem Report has been issued to evaluate options to correct this condition.

Checkl ist Section 5.3 Scheduled C~om 1etion Complete preliminary evaluation by end of first refueling outage.

7)

Limit marks will be added on the SPDS Level II displays.

5.11 By end of first refueling outage.

8)

The SPDS computer points are not included in routine instrument loop surveillances.

A Problem Report has been issued to identify all SPDS points and to include these points into applicable surveillances.

4.4 Indentify points and begin process of including points in survei llances by end of first refueling outage Note:

The changes to the SPDS defined by the NHPC response to the pre-implementation audit will be completed by the end of the first refuel outage.

Other changes, resulting from the SPDS design evaluation and/or from the man-in-the loop testing will be scheduled as appropriate.

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REGULATORY GUIDE 1.97 BWR TYPE A VARIABLES KEY TO PLANTS PLANT NAME OR05 UNIT 1

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09/03/91 FILE NO.

REGULATORY GUIDE 1.97 BWR TYPE A VARIABLES KEY TO PLANTS PLANT NAME OR05 UNIT 1 OR05 UNIT 3 OR05 UNIT 2 OR06 UNIT 2 OR06 UNIT 1 LP09 OR09 OR12 UNIT 2 OR12 UNIT 3 OR13

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ML18038A661

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