ML18038A661

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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  Constellation icon.png
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)
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Text

V NIAGARA N 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 Nine Nile Point Unit 2 Docket No. 50-220 Docket No. 50-il0 DPR-63 NPF-69 Gentlemen:

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 PDC

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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 Hanagement 'ecords

l, UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of ) Unit l

) Docket No. 50-220 Niagara Hohawk Power Corporation ) and

) Unit 2 Nine Hile Point Nuclear Station ) Docket No. 50-410 CERT I F I CAT I 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. D. T ry t Vice President Nuclear Engineering and Licensing Before of ',

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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 the requirements of NUREG-0737, Supplement 1, taking into be modified to meet 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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Descri tion Checklist Section Scheduled C~om letion

1) Radioactivity control will be added to 2.1.4, 2.2.9, 3.1, 3.3 By end of first the SPDS displays. This includes plant refueling outage overview display (Level I) and additional detail (Level II) display. All five required safety functions will then be displayed on the SPDS
2) Drywell temperature wi 11 be added as a 2.2.10, 2.2.7 By end of first containment integrity parameter refueling outage
3) The SPDS reactor water level parameter has 4.7, 4.8 By end of first displayed invalid/erroneous information or refueling has been'n a false alarm condition greater than outage 5 percent of operation. A work request (HR 162049) has been issued to troublshoot.
4) High and Low Level setpoints will be 5. 10 By end of first re-evaluated as part of the overall refueling SPDS modification. outage.
5) Complete verification and validation (V5V) 4.5, 5.15 By end of first requirements (as identified in the refuel ing pre-implementation audit) i.e. man-in-the-invalidation outage.

loop testing, collect and centrally locate all necessary VKV documentation, test

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ATTACHNENT 1 Descri tion Checkl i st Section Scheduled C~om 1etion

6) The SPDS screens cannot be clearly read 5.3 Complete from the EOP flowcharts. A Problem Report preliminary has been issued to evaluate options to evaluation by correct this condition. end of first refueling outage.
7) Limit marks will be added on the SPDS 5.11 By end of first Level II displays. refueling outage.
8) The SPDS computer points are not included 4.4 Indentify points in routine instrument loop surveillances. and begin A Problem Report has been issued to identify process of all SPDS points and to include these points including points into applicable surveillances. 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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09/03/91 REGULATORY GUIDE 1.97 BWR TYPE A VARIABLES KEY TO PLANTS FILE NO. PLANT NAME OR05 UNIT 1 BROWNS FERRY 1 OR05 UNIT 3 BROWNS FERRY 3 OR05 UNIT 2 BROWNS FERRY 2 OR06 UNIT 2 BRUNSWICK 2 OR06 UNIT 1 BRUNSWICK 1 LP09 CLINTON 1 OR09 COOPER 1 OR12 UNIT 2 DRESDEN 2 OR12 UNIT 3 DRESDEN 3 OR13 DUANE ARNOLD LP12 FERMI 2 OR15 FITZPATRICK 1 LP15 GRAND GULF 1 OR20 UNIT 1 HATCH 1 OR20 UNIT 2 HATCH 2 LP18 HOPE CREEK 1 LP19 UNIT 1 LASALLE 1 LP19 UNIT 2 LASALLE 2 LP20 UNIT 1 LIMERICK 1 LP20 UNIT 2 LIMERICK 2 OR26 MILLSTONE 1 OR28 MONTICELLO 1 OR29 NINE MILE PT 1 (L'F25 NINE MILE PT 2 OR32 OYSTER CREEK 1 OR34 UNIT 2 PEACH BOTTOM 2 OR34 UNIT 3 PEACH BOTTOM 3 LP29 UNIT 1 PERRY 1 LP29 UNIT 2 PERRY 2 OR35 PILGRIM 1 OR38 UNIT 1 QUAD CITIES 1 OR38 UNIT 2 QUAD CITIES 2 LP31 RIVER BEND 1 LP34 SHOREHAM 1 LP39 UNIT 1 SUSQUEHANNA 1 LP39 UNIT 2 SUSQUEHANNA 2 OR49 VERMONT YANKEE 1 LP42 WNP 2

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