ML17298A913
| ML17298A913 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/27/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton F, Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 ANPP-29167-WFQ, GL-82-33, NUDOCS 8404020131 | |
| Download: ML17298A913 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION S EN (RIDS)
ACCESSION NBR;8404020131 DOC ~ DATE: 84/03/27 NOTARIZED! NO, DOCKET FACIL:STN-50 528 Palo Verde Nuclear Station~
Unit ii Arizona Publi 05000528 STN"50-529 Palo Verde Nuclear Stationi Unit 2i Arizona Pub'li 05000529 STN-50-530 Palo Verde Nuclear Station<
Unit 3< Arizona Publi 05000530 AUTH INANE AUTHOR AFFILIATION VAN BRUNTiE,ED Arizona Public Service Co ~
RECIP ~ NAME.
RECIPIENT AFFII IATION KNIGHTONiF ~
Licensing Branch 3
SUBJECT:
Advises that computer-bared safety parameter display installation completed, Safety anaylsis performediper Ltr 82-33iSuppl 1 to NUREG-0737,Observations wi11 be resolved by.Dec 1984
'ISTRIBUTION CODE:
A003S COPIES RECEIVED'-LTR ENCL SIZE TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG 0737(Generic L
NOTES:Standardized plant ~
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LTTR 34 ENCL
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Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos. STN-50-528/529/530 File:
84-056-026; G.l.01.10
Reference:
1.
Letter from E.
E.
Van Brunt, Jr.,
APS, to G.
W. Knighton,
- NRC, (ANPP-23505 WFQ/MAJ), dated April 14, 1983.
2.
NRC letter from D.
G.
- Eisenhut, NRC, to Applicants for Operating
- Licenses, dated December 17, 1982.
Subject:
Supplement 1 to NUREG-0737.
Requirements for Emergency
Response
Capability {Generic Letter No. 82-33).
Dear Mr. Knighton:
As discussed in Reference (1), the Safety Parameter Display System (SPDS) for PVNGS has been designed to provide a
concise display of critical plant variables for control room personnel to aid them in rapidly and accurately determining the safety status of the plant.
The PVNGS SPDS is designed to be operable during normal and abnormal conditions to enable the control room personnel to
{1) assess the safety status of the plant and (2) to determine whether abnormal conditions warrant corrective action.
The installation of the PVNGS SPDS computer based display system has been completed.
The completed system consists of the Data Acquisition System, the Technical Support Center (TSC) computer system and the display Cathode Ray Tubes (CRTs) and their corresponding keyboards.
A portion of the field sensor inputs to the SPDS still require cable termination.
We expect the PVNGS Unit 1 sensor inputs to the SPDS to be installed and tested by fuel load.
As of this date, APS has performed the SPDS Safety Analysis as required by Reference (2).
The safety analysis was performed by evaluating the PVNGS SPDS computer based display system.
The evaluation consisted of the following tasks:
(1) a verification of the SPDS design requirements and capabilities to determine that the actual SPDS design satisfied the 840402013l 840327 PDR ADOCK'5000528 I,*
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Mr.
G.
W. Knighton Page 2
design and capability requirements, (2) a validation of the SPDS design performed (using the scenario method) to test and evaluate the integrated hardware and software of the display system and to determine compliance with the functional, performance and interface requirements
'(3) a human factors review was performed to evaluate the human factors aspects associated with the SPDS displays and terminal equipment and (4) an evaluation of the Safety Function Groups and their associated parameters was performed to determine if the selected parameters, correlated to those that the control room operator is required to monitor during abnormal and emergency plant conditions.
During the process of performing the above
- tasks, several observations were identified,', and documented..
These observatio'ns are-currently under review by APS management for their'isposition'chedules.
'ii We expect to have the observations resolved by about
- December, 1984 and will have our final, summary report confirming the acceptability of the SPDS available at tha't 'ime.
This supercedes our.schedule previously provided in Reference (1).
If you have any further questions on this matter, pl'ease~ contact me.
Very truly yours,
- 2. P,Vcu~
E.
E.
Van Brunt, Jr.
APS Vice President, Nuclear ANPP Project Director EEVB/MAJ/s p cc:
E. A. Licitra A.
C.
Gehr
E y
I.