ML17299B208

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Informs That SPDS Experienced Difficulties in Achieving 99% Sys Availability,Per NUREG-0696.Caused by Difficulty in Transmitting Field Data from Sensor Inputs to SPDS Computer Sys.Mods to Be Implemented Identified
ML17299B208
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/22/1986
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Knighton G
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0696, RTR-NUREG-696 ANPP-36303-EEVB, TAC-56654, TAC-62796, NUDOCS 8604240215
Download: ML17299B208 (8)


Text

REQULAT Y INFORNATION DISTRIBUTIO YSTEN (RIDB)

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ACCESSION NBR: 8b042402i 5 DOC. DATE: B6/04/22 NOTARIZED: NO FACIL: STN-50-528 Palo Verde Nuc.1eav Stations Unit ii Av'i zona Pub 1 i STN-50-529 Palo Vev de Nuclear Btationi Unit 2i Arizona Publi AUTH. NANE AUTHOR AFFILIATXON VAN BRUNT'. E. Av izona Nucleav Potoer Pv object (fov'mev 1g Av i zona f"ubiic Serv RECXP. NAME RECIPIENT AFFILIATION KNIQHTONi Q. M. PMR Pv oge'ct Directov ate 7

SUBJECT:

Informs that BPDB experienced difficulties in achieving 99/

sos unavai labil it)i pev'UREQ-0696 Caused bg di fficultg in tv'ansmitting field data from sesnsov'nputs to SPDS computev sos Nods to be implemented identified.

DISTR IBUTlON CODE: A003D COP IES RECEIVED: LTR ENCL SI ZE:

TITLE: OR/Licensing Submittal: Supp 1 i to NUREQ-0737(Qenev ic Ltr 82-33)

NOTES:Standardized plant; 05000528 Standav dized plant. 05000529 RECIPIENT COPIEB REC IP 1 ENT COPIES XD CODE/NAl'1E LTTR ENCL ID CODE/NAME LTTR ENCL PNR-B *DTB i PNR-B EB i PNR-B PEICSB 2 PNR-B FOB i PMR-B PD7 LA i PMR-B PD7 PD 7 LICXTRAiE i PNR-B PEI CSB PWR-B RSB i INTERNAL: ADN/LFNB IE/DEPER/EPB NRR BMR ADTB NRR PAULSONI M NRR PMR-A ADTB NRR PMR-B ADTS NRR/DHFT/HFIB NRR/DHFT/NTB, NRR/DSRO ENRIT /EIB NRR/DSRO/RSIB EQ FILE RQN5 EXTERNAL: 24X LPDR NRC'DR NBIC TOTAL NUNBER OF COPIEB REQUIRED: LTTR 40 ENCL

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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 April 22, 1986 ANPP-36303-EEVB/MAJ/98.05 Director of Nuclear Reactor Regulation Attention: Mr. George W. Knighton, Project Director PWR Project Directorate //7 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station Units 1 and 2 Docket Nos. STN 50-528 (License No. NPF-41)/529 (License No. NPF-46)

Safety Parameter Display System File: 86-056-026

Reference:

(1) PVNGS Unit 2 Facility Operating License, Number NPF-46, dated December 9, 1985.

(2) Letter from E. E. Van Brunt, Jr., ANPP, to G. W. Knighton, NRC, dated November 8, 1985 (ANPP-33965).

Subject:

Schedule for NUREG-0737, Supplement 1, Items.

(3) Letter from E. L. Jordan, NRC/IE, to all Nuclear Power Reactors dated February 13, 1986.

Subject:

IE Information Notice 86-10 Safety Parameter Display System Malfunctions.

(4) PVNGS Unit 1 Facility Operating License, Number NPF-41, dated

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June 1, 1985.

Dear Mr. Knighton:

The licensing condition in Reference (1), Attachment 2, Item (d) states, "By April 30, 1986, the Safety Parameter Display System (SPDS) shall be ready for operation. The system shall not be used by the operators for accident evaluation until the NRC staff has approved its use."

Additionally, Reference (2) stated that the SPDS design for PVNGS Units 1 and 2 is identical and both Units would be ready for the NRC Staff's audit by April 30, 1986.

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Mr. G. W. Knighton Safety Parameter Disply System ANPP- 36303 Page 2 The purpose of this letter is to inform you 'that the PVNGS SPDS has experienced diff1culties 1n achieving the 99X system availabil1ty goal as established by NUREG&696, and we are currently evaluating this problem. The SPDS availability for PVNGS Unit 1 has steadily increased during the completion of the power ascension test program. Actual operational data from the unit is required to fine tune the SPDS to assure reliable data is being displayed. This data has been difficult to obtain consistently, since the unit has been undergoing a power ascension test program. Also, we have been experiencing availability problems with the Unit 2 SPDS since we have been unable to obtain actual plant data.

Additionally, the NRC has recently published IE Information Not1ce 86-10, Reference (3), which provides new generic concerns for implementing an SPDS.

We require additional time to identify whether any of the noted deficiencies ex1st at PVNGS and, if any deficiencies exist, to provide a plan and schedule before the SPDS is considered ready for operation. In to resolve the concern light of this IE Informat1on Notice 86-10 and the availability problem described above, we have decided to not consider the SPDS "ready for operation" at this time. We expect that the SPDS for Units 1 and 2 will be ready for operation by October 30, 1986.

The principal problem associated with ach1eving a high system availability fo' the Unit 1 and Unit 2 SPDS lies in the transmission of the field data from the sensor inputs to the SPDS computer system. We are currently evaluating this problem and thus far have 1dentified several mod1fications to be implemented on the system. These include rewiring between the SPDS and the field inputs from the rod bottom contacts, and the Control Room Essential Filtrat1on Actuation System (CREFAS). Add1tionally, we have identified the need to replace some cards associated with the Radiation Monitoring System data link to the SPDS. As of this date, we are still evaluating the problem of data transmission and use from the field inputs to the SPDS computer system. Our evaluation may identify that further modifications are needed to increase the system availability. At th1s time, we believe that we will be able to address any new problems our evaluation may identify, and have the problems corrected by October 30, 1986 so that the SPDS for Units 1 and 2 will be ready for operation and NRC audit.

Because of the availability problems discussed above, our operations staff has been unable to use the system on a routine basis to become familiar with the operation and the information the system can provide. Operator training on the use of the SPDS has been provided, but, because of the ava11ability problems and the NRC concerns noted in IE Information Notice 86-10, we have decided to provide additional training on the- SPDS to the operators in the operator requalification training program. A revised lesson plan is being developed and the operators will be retrained on the use of the SPDS by October 30, 1986.

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Mr. G. W. Knighton Safety Parameter Disply System ANPP- 36303, Page 3 If you have any questions or require additional information, please call Mr. William Quinn of my staff.

Very truly yours,

. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/MAJ/dk cc: A.C. Gehr E. LLcitra R. Zimmerman

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