ML17300A563
| ML17300A563 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/29/1986 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-38447-JGH, TAC-56654, TAC-62796, TAC-64581, NUDOCS 8610090515 | |
| Download: ML17300A563 (8) | |
Text
DOCKET 5 05000528 05000529 05000530
SUBJECT:
Infovms that addi info v e BPDB isolation device testing not supplied bg 860901 deadlinei pev 860730 request. Info vill be submitted bg 861215. Reasons fov delaM listed. Requested testlvlg of isolators incorporated into pv esent schedule.
DISTRIBUTION CODE:
B021D COPIEB RECEIVED: LTR ENCL SIZE:
TITLE: OR/Licensing Submittal:
Combined General Distv'i ution REQULATO INFORMATION DISTRIBUTION TEN (RIDS)
ACCESSION NBR: 8610090515 DOC. DATE: 86/O'P/29 NOTARIZED:
NO FACIL:BTN-50-528 Palo Vev de Nuclear Stationi Unit ii Av izona Pub li BTN-50-529 Palo Vev'de Nuclear Stations Unit 2i Av'izona Publi STN-50-530 Palo Vev'de Nucleav Stationi Unit 3i Av'izona Pub li AUTH. NANE AUTHOR AFFILIATION HAYNES> J. Q.
Av'izona Nucleav'ouev Prospect (formerly Av i zona Public Serv REC IP. NANE RECIPlENT AFFILIATION KNIQHTON> Q. M, PWR Pv object Directorate 7
NOTES: Standav'dized plant. N. Davisi NRR: 1CM.
Standav'di zed p lant. N. Davi si NRR: 1Cg.
Standardized plant. N. Davisi NRR: 1Cg.
05000528 0 500052'P 05000530 NP~ I/NIB 04 REC lP IENT ID CODE/NANE PNR-B ADTS PNR-B PEICSB PWR-B PD7 LA LICITRAiE 01 PWR-B RBB INTERNAL: ACRB 29 ELD/HDB3 NRR PWR-A ADTS NRR/
IR COPIES LTTR EN 1
2 1
1 1
8 1
1 1
1 1
CL RECIPIENT ID CODE/NAME PWR-B EB PWR-B FOB PWR-B PD7 PD 05 PWR-B PEICSB ADM/LFNB NRR BWR ADTS NRR PWR-B ADTS NRR/ORAB RQN5 COP IEB
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1 EXTERNAL: LPDR NSIC NOTES:
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PHOENIX, ARIZONA85072-2034 September 29, 1986 ANPP-38447-JGH/GS/98.05 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Project Director PWR Project Directorate II7 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station Units 1, 2 and 3
Docket No.
STN 50-528 (License NPF-41)
STN 50-529 (License NPF-51)
STN 50-530 Safety Parameter Display System (SPDS)
File:
86-A-056-026 86-C-056-026; J.9.02
Reference:
(1)
Letter dated July 30,
- 1986, from E.
A. Licitra,
- NRC, to E. E. Van Brunt, Jr.,
ANPP.
Subject:
Request for Additional Information Safety Parameter Display System for Palo Verde.
(2)
Letter dated January 10,
- 1986, from G.
W. Knighton, NRC, to E.
E.
Van Brunt, Jr.,
ANPP.
Subject:
Request for Additional Information Safety Parameter Display System Isolation Devices.
(3)
Letter dated April 22,
- 1986, from E.
E.
Van Brunt, Jr.,
- ANPP, to G.
W.
- Knighton, NRC.
Subject:
Safety Parameter Display System.
Dear Mr. Knighton:
In Reference (1), the staff requested that ANPP supply additional information concerning the SPDS isolation device testing by September 1,
1986.
The referenced letter required that ANPP perform a
Maximum Credible Fault (MCF) test in the transverse mode on the non-IE output of different types of SPDS isolators used in PVNGS Units 1, 2, and 3 and submit revised responses to the questions posed by the staff in Reference (2).
As previously discussed with NRC staff, it was not possible to meet NRC's requested date of September 1, 1986, for the followin'g reasons:
(1)
The requirement to conduct the isolation device test is a new work scope item, previously unidentified.
86i0090515 860929 PDR ADQCK 05000528 P
a o
c
Mr. George M. Knighton Safety Parameter Display System (SPDS)
ANPP-38447 Page 2
(2)
The original scope of work agreed upon to declare SPDS ready for operation (Reference 2) upon which the Unit 2 License Condition 2.C(8) was
- based, has a
schedule which cannot accommodate the additional isolation device testing and analysis.
(3)
Personnel involved in completing the milestones for getting SPDS ready for operation in a timely manner cannot be diverted at this time to perform and evaluate the new test proposed by the staff without jeopardizing the original schedule.
(4)
Supplying the requested information to the staff will require ANPP to devote a significant amount of time to gather, analyze and review the test data, which by itself will constitute a separate schedule.
Considering the above
- reasons, ANPP will submit the response to the staff request (Reference 1) by December 15, 1986.
This schedule and the reasons discussed above have been discussed with the staff on multiple occasions during the months of August and early September.
ANPP has,
- however, decided to incorporate the NRC's requested test of the isolators into the present schedule set for meeting the Unit 2
License Condition.
This decision is based on the fact that determination of whether the isolators are adequate for the SPDS to be ready for operation by October 30, 1986, plays an important role in meeting the Unit 2
License Condition 2.C(8).
ANPP recognizes that if the isolators fail the MCP testing to be conducted prior to October 30,
- 1986, the SPDS although functional, cannot be declared ready for operation.
Therefore, Unit 2 License Condition 2.C(8) would not be met.
As a
contingency in the event of failure of isolators during the test requested by the staff, ANPP is preparing an amendment request submittal for the Unit 2 operating license.
This amendment request will be submitted in the near future.
A t
Mr. George W. Knighton Safety Parameter Display System (SPDS)
ANPP-Page 3
If you have any questions regarding this
- matter, please contact Mr. W. F.
Quinn of my staff.
JGH/GS/dim Very truly yours, (c,J~,
J.
G.
Haynes Vice President Nuclear Production cc:
0.
M.
E. E.
E. A.
A. C.
R.
P.
DeMichele Van Brunt, Jr.
Licitra Gehr Zimmerman
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