ML20247M845
| ML20247M845 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/19/1998 |
| From: | Tam P NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-MA1431, TAC-MA1432, NUDOCS 9805260393 | |
| Download: ML20247M845 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 4001 May 19,1998 MEMORANDUM FOR:
Docket File:
FROM:
Peter S. Tam, Senior Project Manager
- Project Directorate 11-2 Division of Reactor Projects - 1/II M
Office of Nuclear Reactor Regulation i
SUBJECT:
CATAWBA NUCLEAR STATION - ISSUES FOR ONSITE REVIEW OF THE 1997
SUMMARY
OF ACTIONS PERFORMED UNDER 10 CFR 50.59 (TAC MA1431 AND I
MA1432)
The attached document was transmitted by electronic mail today to John Glenn and Mike Kitlan of Duke Energy Corporation (DEC) to prepare DEC for an upcoming onsite review. The document lists the 10 CFR 50.59 evaluations that I selected to review onsite, and questions on the report summarizing the Catawba changes made under 10 CFR 50.59 in 1997. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
l Docket Numbers 50-413 and 50-414 Distnbution PUBLIC H. Berkow
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Please have the 50.59 analysis for the following changes available:
1.
CE-3489, Add Vent to Spent Fuel Cooling System Piping 2,
CE-5009, incorporate Revised Westinghouse Ice Basket Information into Controlled Drawings 3.
CE-60278, Upgrade Conventional Low Pressure Service Water System -
Pump A Flow Capacity -
4.
CE-8390,- 2.5-inch Penetratiori in Steam Generator 2A for Foreign Object Retrieval 5.
CE-8592, Cut and Cap the Nuclear Service Water System Retum Line from the Diesel Generator Engine Cooling Water System Heat Exchanger 6.
CE-8652, Revise the Setpoints of Reactor Coolant Pumps 2A and 2D 7.
CE-8710, Revise RHR Pump Miniflow Valve Pressure Setpoints 8.
CE-9241, Modify Support Mechanism for the CRDM and incore Instrumentation System Backdraft Damper j
i 9.
CE-7934 and CE-7956, Removal of Straightening Section from Fuel Pool Ventilation System Air Flow Monitors 10.
CN-21329, Operator Aid Computer Replacement 11.
CN-11373, Modify Main Steam Isolation Valve Control Circuit 12.
CN-504311nstrument Air System Dryer Automatic Operation, Flow instrumentation, Emergency Lighting, and Relief Valve Replacement l
' 13.
CNC-1223.03-00-0030, Engineering Evaluation to Support Natural Circulation Following Reactor Coolant System Vacuum Fill 14.
Removal of Forward Flow Test Requirement from Inservice Test Program for l:
. Valve 1(2)N148, the Cold Leg Accumulator Nitrogen Supply Check Valve 15.
The Compensatory Actions for Excavation in Area of Buried Nuclear Service Water System Piping 16.
Revision of Core Operating Limits Report to increase the Limit on Boron Concentration 17.
Revision to Core Operating Limits Report Mode 4 Reactor Makeup Water Pump Flowrate Limit 18.
Revisbn to the Core Operating Limits Report to Reflect Changes in the Loss of Coolant Accident (LOCA) Power Peaking Limits 19.
Specifica0on Change to Coatings Specification DPC-1167.01-00-0001 l
20.
(Change 144) Revision 1a to Topical Report DPC-NE-1003-A, Rod Swap
{
Methodology for Startup Physics Testing 21.
(Change 145) Revision 2a to Topical Report DPC-NE-3002, UFSAR Chapter i
15 System Transient Analysis Methodology.
j
. 22.
(Change 157) Ciention of Procedure MP/2/A/7150/115, Core Exit i
Thermocouple Nezzle Disassembly and Reassembly 23.
Procedure TT/2/A'9300/023, Test for Valve NV-1(2)813, Check Valve Between Train A cf the Residual Heat Removal System and the Centrifugal y
Charging Pumps 24.
Procedure PT/0/A/4150/012A, Isothermal Temperature Coefficient of I
Reactivity Measurecnent
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25.
Revision to Procedure MP/0/A/7150/042, Reactor Vessel Head Removal and Replacement 26.
Revision to Procedure PT/s/A/4200/01C, Containment Isolation Valve Leak j
Rate Test, to Allow Testing of the Standby Makeup Containment Header l
Check Valve 2NV-874 Questions (note that those that appear to be missing are not questions, i.e. don't worry about them):
1.
Minor Modification CE-61306, "... Reactor Coolant Pump 1D#1 seal leakoff line failed.. " Was this failure reported? If so, please reference the report.
i 2.
Minor Modification CE-8626. Can Duke revise a Westinghouse manual? Is l
there an agreement which permits such revision?
i 3.
Minor Modification CE-8652. Does each RCP have its own vibration alarm setpoint (i.e. 2A and 2D different from 2B and 2C)? How about Unit 1 RCPs?
4.
Minor Modification CE-8821, What is the Heating Water System?
6.
Minor Modification CE-61264. What was the reason for this modification (i.e.
. what was wrong with the motor-operated original design)?
7.
Minor Modification CE-61272,61277,61278. Tech. Spec. 3.5.1 specifies water volume between 7630 and 8079 gallons. What made accumulator 2C different such that it did not need this modification?
10.
Nuclear Station Modification CN-11339, regarding vital instrumentation and control power batteries. How is the " interpretation associated with Tech.
Spec. 3.8.2.1" changed?
11.
Nuclear Station Modification CN-11371, regarding deletion of auxiliary feedwater flow optimization and pump runout logic. This was presumably i
done during the SG replacement (1996). Besides, you have already reported this in your 1996 summary (March 31,1997). Reasons?
l L
12.
Nuclear Station Modification CN-9150, scaffolding in lower containment. This CN "will be used in support of access to perform Steam Generator Replacement Project,,,," Presumaly this took place in 1996. Reasons for reporting in 1997?
13.
CN-19710, SG blowdown system piping. This CN again refers to the SG replacement project. Reason for reporting in 19977 l
ll
~
14 CN-21371, deletion of AFW flow optimization and pump runout logic. Is this change a counterpart to CN-11371 for Unit 1? When was this change made?
15.
CN-21375, upgrade allowable design temperature for AFW piping. Is this related to CN-11375 that was summarized in your March 31,1997 report?
~ Was this change also prompted by inspection Report 96-05, and addressed by Duke's June 16,1997, letter?
l 16.
CN-50472, Standby Nuclear Service Water Pond (SNSWP) level increase.
SNSWP level was raised from 571' to 572' above MSL (reference CE-5017 and FOL Amendments 152/144. What led to this further increase to 574' above MSL7 17.
NSM-50419, Cryo Ice Machine. Does it make ice for the ice condenser, or does it have other functions?
18.
Some changes summarized in this report are not serialized (i.e. no CN, CE numbers). For example, change 114 thru 128. What categories are these changes? How do you file the documentation?
19.
(Change 130) Residual Heat Removal System Operability Evaluation Due to Pressurization of Discharge Piping. Did you find out from where the nitrogen originated?
)
20.
(Change 143) Change to the Bases Associated with Technical Specification 3/4.3.3.1. "A change is required for the' Technical Specifications Bases 3/4.3.3.1" When will this change be made?
22.
Revision 20 to PT/1/A/4250/03E, Aux Feedwater System Discharge Control l
Valve Throttling Procedure. Was CN-11383 summarized in last year's 50.59
- report? If not, where was it summarized?
23.
(Change 204) Revision 6 to PT/1(2)/A/4400/03D. How many component cooling pumps are normally needed?
l 24.
(Change 208) Revision to EPla(2)/A/5000/E-0 etc. Were these changes prompted by an NRC inspection? If so, please cite the inspection report.
25.
(Change 211) Revision to Procedure MP/0/A/7150/067. "The Technical Specification Bases have been changed....." Please cite the documentation (Duke submittal and NRC issuance).
26.
(Change 235) Temporary Modification W/O 96091303. "The valve will be closed, which is its safety position." Does this valve perform safety functions? What system is the valve on?