ML17299A816
| ML17299A816 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/29/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 ANPP-34129-EEVB, NUDOCS 8512030543 | |
| Download: ML17299A816 (14) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 851203054'3 DOC, DATE: 85/1 1/29 NOTARIZFD:
NO DOCKET FACIL:STN-50 529 Palo Verde Nuclear Stationi Unit 2i Arizona Publi 05000529 AUTH,NAME, AUTHOR=- AFF'ILIATION VAN BRUNT>E.E,"
Ar izona. Nuclear Power Project (formerly Arizona. Publ jc Serv RECIP',NAME RECIPIENT AFFILIATION KNIGHTONiG ~
WE PHR Project Directorate 7
SUBJECT:
Responds tol 851127 request for info.
8 justifications for interiim operation re radiation monitors>> for, plantgper NUREG-0737iSuppl I..Measures taken re factors contributing to inope'rable radiation monitors l.isted DISTRIBUTION CODE:
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TITLE: Licensi'ng Submittal:
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Arizona Nuclear Power Project P.O. BOX52034
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PHOENIX, ARIZONA85072-2034 November 29, 1985 ANPP 34129 EEVB/VFQ/JKO Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Project Director PWR Project Directorate 87 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington,'.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No.
STN 50-529 JU8tification for Interim Operation related to the Radiation Monitors File:
85-056-026 '.1.01.10
Reference:
Letter to G.
W. Knighton,
- NRC, from E.
E.
Van Brunt, Jr.,
- ANPP, dated November 8,
1985 (ANPP-33965);
Subject:
Supplement 1
to NUREG-0737 Schedule
Dear Mr. Knighton:
Per telecon on November 27,
- 1985, ANPP agreed to provide information and ju8tifications for interim operation concerning the Radiation Monitors for Unit 2.
The schedule for the Radiation Monitors is as follows:
(1) Monitors which are subject to Technical Specification requirements. will be operable prior to the mode for which they axe required without entering a technical specification action statement; (2) Regulatory Guide 1.97 monitors will be operable per the commitments in the referenced letter; (3) Monitors which are not subject to Technical Specification requirements and are not di8cu8sed in the referenced letter will be operable as decribed in the attachment to this letter.
The attachment to this letter also provides compensatory measures and justifications for interim operation for those monitors which will not be completed prior to initial criticality.
Prior to inital criticality, there is no reactivity in the system.
8512030543 8511~9 PDR ADOCK'05000529 PDR o~t
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Mr. George W. Knighton Justification for Interim Operation of Radiation Monitoring System ANPP-34y29 Page Two Several factors, as discussed
- below, have contributed to the Unit 2 radiation monitors being inoperable at this time.
Measures have been taken to correct these conditi'ons.
Vendor support is needed in design areas primarily for Hardware Design
- Changes, Software Design Changes and Technical Clarification.
This support from the vendor has historically been slow and, in some
- cases, lacked clarity.
To resolve these
- problems, ANPP has contracted the services of two vendor engineering personnel to work strictly for this project.
The overall level of support has increased and has indications of continuing to increase.
In addition, the project has contracted for two technicians from the vendor on a short duration basis.
This is to facilitate more rapid troubleshooting and increase the PVNGS personnel knowledge of the system.
2.
Maintenance (I&C) Knowled e Level As with all highly technical systems, it takes time for personnel to learn the system.
In the 3
months of intense concentration on this particular
- system, the technicians have progressed significantly on the learning curve.
This, of course, will continue to improve with time.
Spare parts is an industry wide problem, not specifically associated with this system but definitely a factor.
Due to the complexity of the
- system, most failures have to be resolved on a circuit board level.
Faulty circuit boards are removed and then sent back to the factory (vendor) for repair.
In June,
- 1985, an order to increase the spare parts inventory by approximately 50X was placed with the vendor.
Due to long lead times, the bulk of this order is gust beginning to become available on site.
The vendor has also committed to increase production for PVNGS to approximately 50X of factory output.
To
- date, the prospect has expected delivery dates ranging from the present to 6 months from now.
4.
PVNGS Unit 1 Su ort Due to commitments for Unit 1, radiation monitor parts were transferred from Unit 2 for use in Unit 1.
These parts, for the most part, have been replaced in Unit 2 and, if the need arises, Unit 3 parts will be used to support Units 1 and 2.
- Also, the need for spare parts in Unit 1 has dropped off significantly.
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Mr. George W. Knighton Justification for Interim Operation of Radiation Monitoring System ANPP-34129 Page Three The pro)ected completion dates discussed in the attachment are the PVNGS commitment for completion.
If, for any unforeseeable reason we cannot meet this commitment, we will discuss it with the staff at that time.
If you have any further questions, please contact Mr. William F. Quinn.
Very truly yours, EEVB/WFQ/JKO/dim E. E.
Van Brunt, Jr.
Executive Vice President Prospect Director
,cc:
E. Licitra M. Ley R. P.
Zimmerman A. C. Gehr
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Attachment to ANPP 34129 ATTACHMENT PROCESS MONITORS LI UID MONITOR NUMBER DESCRIPTION PROJECTED COMPLETION RU-4, 5
Steam Generator Blowdown Monitors June 30, 1986 Justification for Interim 0 eration (JIO):
Steam Generators will,be sampled every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in Mode 1 to 4 for gamma isotopic activity.
The condenser, vent effluent monitors (RU-141/142) must be on line for Mode 4
entry and these will indicate in the ev'ent of contamination in the secondary system.
RU-2, 3, RU-6 Essential Cooling Water Monitors Nuclear Cooling Water Monitor June 30, 1986 JIO:
Prior to these monitors becoming fully operable, but only after initial criticality and when the applicable train/system is in operation, the applicable train will be sampled on a weekly basis for gamma isotopic activity.
These monitors are for trend indication only and the buildup of radioactivity in these trains is slow and significant leakage would be identified via water balance inventories on affected system.
RU-7 RU-204 RU-265 Auxiliary Steam Condensate Process Radiation Monitor Gas Stripper Monitor Initial Criticality Initial Criticality Initial Criticality NOTE:
Samples will be taken in accordance with Station Procedures.
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Attachment to ANPP 3%129 ATTACHMENT
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PROCESS MONITORS ATMOSPHERE MONITOR NUMBER DESCRIPTION PROJECTED COMPLETION RU-8 RU-9 RU-10 Ru-14 Auxiliary Building Ventilation Exhaust Auxiliary Building Lower Level Vent Exhaust Auxiliary'Building Upper Level Vent Exhaust Radwaste Building. Vent Exhaust June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 JIO:
1 Prior to these monitors becoming fully operable, but only after initial criticality, the associated sample stream will be monitored via a continuous air monitor (CAM).
These CAM's will be of a portable type with preset alarms and recorder.
These CAM's will be checked daily.
.The atmosphere that these monitors sample during normal operation is the exhaust through the Plant Vent which is sampled by Technical Specification Monitor RU-143.
These monitors are used to localize the source of the contamination and the CAM's will provide similar indication.
RU-15 Waste Gas Vent Exhaust June 30, 1986
'IO:
No compensatory measures will be taken.
The atmosphere that this monitor would normally sample is additionally sampled by the following Technical Specification Monitors RU-12 upstream and RU-143 downstream.
RU-34 Refueling Purge Exhaust Monitor June 30, 1986 JIO:
No compensatory measures will be taken.
The atmosphere that this monitor would normally sample is additionally sampled by the following Technical Specification Monitors RU-1 (containment atmosphere) upstream and RU-143 (plant vent) downstream.
NOTE:
Samples will be taken in accordance with Station Procedures.
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Attachment to, ANPP 341'29 ATTACHMENT (Continued)
AREA RADIATION MONITORS MONITOR NUHBER DESCRIPTION PROJECTED COMPLETION Ru-16 RU-17 RU-33 RU-18 RU-20 RU-21 RU-22 RU-23 RU-25 RU-26 RU-27 RU-28 Containment Operating Level Monitor Containment Incore Area Monitor Refueling Machine Area Monitor Control Room Area Solid Waste Processing Solid Waste Storage Area Loading Bay Area Radiochemical Lab Area Controlled Machine Shop Area Sample Room Area Waste Solidification Area Waste Solidification Area Initial Criticality Initial Criticality Initial Criticality June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 June 30, 1986 JIO:
These areas will be monitored via Portable Area Monitors after initial criticality with preset local alarms and will be checked on a daily basis.
These monitors are utilized for area radiation levels for personnel working in the area and this indication will be covered by the use of the portable area monitors.
NOTE:
Samples will be taken in accordance with Station Procedures.
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