ML17303A311
| ML17303A311 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/20/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 ANPP-40173-JGH, TAC-64580, TAC-64581, NUDOCS 8702260212 | |
| Download: ML17303A311 (12) | |
Text
REQULATO INFORNAT ION DISTRIBUTION:.
<<TEJ'f (R IDB E
ACCEBSIQN NBR: 87022602 12 DOC. DATE: 87/02/20 NOTARIZED:
NO DOCKET ¹ FACIL:BTN-50-530 Palo Verde Nuclear Stations Unit 3> Arizona Pub li 05000530 AUTH. NANE AUTHOR AFFILIATION HAYNES> J. Q.
Arizona Nuclear Pouer ProJect (formerly Arizona Public Serv REC IP. NANE RECIPIENT AFFILIATION KNIQHTQN> Q. W PWR Prospect Directorate 7
SUB JECT:
Provides status of NUREQ-0737'uppl 1 i tems.'.Wal kdoen identified. 16 human engineering discrepancies:
which remain op en.
DISTRIBUTION CODE:
AOOSD COPIES RECEIVED; LTR l
ENCL
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TITLE: OR/Licensing Submittal:
Supp' to NUREQ-0737(Generic Ltr 82-33)
NOTES: Standardized.
plant. N. Davis> NRR: jCg.
05000530 REC IP IENT ID CODE/NAl'fE PWR-8 ADTS PWR-8 PEICBB PWR-8 PD7 LA LICITRAiE PWR-8 RSB INTERNAL:
ADJ f/LFJ f8 NRR BWR ADTS NRR/DSRO El'fRIT NRR/DSRO/RSIB EXTERNAL LPDR NSIC NOTES:
CQP IES LTTR ENCL 1
2 2
1 1
1 1
1 0
1 1
1 RECIPIENT ID CODE/NAKE PWR-8 EB PWR-8 FOB PWR-8 PD7 PD PWR-8 PEICSB IE/DEPER/EPB NRR PWR-8 ADTS
/EIB REG FILE 01.":
1 7
7 1
3 3
1 1
1 1
1 1
TOTAL NUJ'fBER OF COPIES REQUIRED:
LT1R 30 ENCL 29
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Arizona Nuclear Power Project P.O. BOX 52034
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PHOENIX. ARIZONA85072-2034 February 20, 1987 ANPP-40173-JGH/BJA/98.05 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Project Directox PWR Project Directorate 87 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No.
STN 50-530 Status of NUREG-0737, Supplement 1 Items File:
Dear Mr. Knighton:
The attachments to this letter provide the status of the NUREG-0737, Supplement 1 items for PVNGS Unit 3.
A schedule is provided for any of the items that are not expected to be completed before Unit 3 fuel load.
If you have any questions on this matter, please contact Mr. W. F. Quinn of my staff.
Very truly yours, J.
G. Haynes Vice Pxesident Nuclear Production JGH/BJA/dim Attachments cc:
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M. DeMichele E. E. Van Brunt, Jr.
E. A. Licitra R. P.
Zimmerman J.. B. Martin A. C. Gehr (all w/a)
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ATTACHMENT 1 STATUS OF NUREG-0737 SUPPLEMENT 1 ITEMS (1)
SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
The PVNGS Unit 3
SPDS will be ready for operation by issuance of the Unit 3 Operating License with the excepti'on of the following displays:
i)
Subcooled margin ii)
Core exit thermocouples hot leg temperature iii) Reactor vessel outlet plenum level iv)
Reactor vessel upper head level v)
Control element assembly position These displays cannot be completed prior to issuance of the Unit 3
Operating License due to the fact that the instrumentation associated with the displays is not installed until after the fuel loading process.
These displays will be completed prior to exceeding 5X power.
(2)
DETAILED CONTROL ROOM DESIGN REVIEW (DCRDR)
(3)
A walkdown of the PVNGS Unit 3'ontrol Room has identified 16 Human Engineering Discrepancies (HEDs) which remain open.
The HEDs identified are items that are required in order to put the finishing touches on the Unit 3 control room.
Only minor work activities, such as correcting some control board labeling discrepancies, are required to close out these HEDs.
These work activities will be completed prior to issuance of the Unit 3 Operating License.
All other HEDs required for Unit 3
fuel load have been completed.
REGULATORY GUIDE 1.97 REVISION 2 INSTRUMENTATION,;
I Instrumentation for the Regulatory Guide 1.97 variables is described in Table 1.8-1 of the PVNGS FSAR (Amendment 16).
For PVNGS Unit 3, this instrumentation'as been installed, tested, and is considered functional with the exception of the instrumentation listed in A'ttachment 2.
A schedule is provided for the instrumentation that will not be completed prior to issuance of the Unit 3 Operating License.
(4)
EMERGENCY OPERATING PROCEDURES (EOPs)
The EOPs for PVNGS Unit 3 have been implemented.
The Unit 3 EOPs are in accordance with Revision 2
of CEN-152 and the PVNGS plant-specific technical guidelines.
It should be noted that the,NRC Staff concerns from the July 12, 1986 reactor trip at PVNGS are still under discussion with the NRC Staff.
.0 II I
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ATTACHMENT 1 (Continued)
(5)
EMERGENCY RESPONSE FACILITIES (ERFs)
The ERFs associated with PVNGS Unit 3 are complete with the -exception of the outstanding items listed under items (1) and (3) above.
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ATTACHMENT 2 REGULATORY GUIDE 1.97 INSTRUMENTATION VARIABLE VARIABLE TYPE CATEGORY VARIABLE SCHEDULE FOR COMPLETION JUSTIFICATION Degrees of Subcooling Prior to 5X Power Commitment for 5X power is covered'nder Inadequate Core Cooling Instrumenta-tion (ICCI) commit-ments discussed in SSER 6 22.II.F.2.
Neutron Flux Power Prior to Mode 3
Schedule is in accor-dance with Technical Specification 3.3.3.6 requirements for neu-tron flux monitors.
Core Exit Temperatures Prior to 5X Power Commitment for 5X power is covered under ICCI commit-ments discussed in SSER 6
22.II.F.2.
Coze Exit Thermo-couples are installed after initial fuel loading as part of the incore instrumen-tation.
Coolant Level in Reactor Prior to 5X Power Commitment for 5%
power is covered under ICCI commit-ments discussed in SSER 6
22.II.F.2.
The Reactor Vessel Level Monitoring System (RVLMS) probes are installed during reactor vessel head assembly after ini-tial fuel loading.
Analysis of Primary Coolant Prior to 5X Power'his commitment is, in accordance with pre-vious commitments for Post Accident Sampling System (PASS) opera-bility.
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ATTACHMENT 2 (Continued)
VARIABLE VARIABLE TYPE CATEGORY E
VARIABLE Primary Coolant and Sump Samples Containment Air Sample SCHEDULE FOR COMPLETION Prior to 5X Power Prior to 5X Power JUSTIFICATION PASS (see above)..
PASS (see above).
Radiati'on Level In Prior 'to Circulating Primary Initial Coolant Criticality Primary coolant radia-.
tion monitors 3J-,SQA-RU-150 and 3J-SQB-RU-151 will be tested prior to initial criticality.
Addi-tionally, no inventory of fission products will exist in the core prior to. initial criticality..
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