ML20235A725
| ML20235A725 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/30/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8707080519 | |
| Download: ML20235A725 (36) | |
Text
Dunn Powna GOMPANY P.O. HOX 33180 citAHLorrE, N.C. 28242 IIAL U. TUCKER reternown vme raensomwr (704) 07'#4538 wuottaa emonvotion 1
)
June 30, 1987 1
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Subject:
Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 z
1986 10 CFR 50.59 Report
Dear Sir:
In accordance with the requirements of 10 CFR 50.59, please find attached the Summary of FSAR Test Abstract Changes, the Tummary of Nuclear Station Modifications and Exempt Change Variation Notices, and the Summary of Procedure Changes, Tests, and Experiments, which were completed under'the provisions of 10 CFR 50.59 during the period from January 1, 1986 to December 31,-1986.
In addition, there were no changes made to the Fire Protection Plan that are reportable under License Condition No. 8 of Operating License NPF-35.
Very truly yours, 1
Hal B. Tucker JGT/60/sbn Attachments xc:
Dr. J. Nelson Grace, Regional Administrator.
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P. K. Van Doorn.
NRC Resident Inspector
/
Catawba Nuclear Station
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1 of 4 i
CATAWBA NUCLEAR STATION Summary of FSAR Test Abstract Changes Completed Under 10CFR50.59 for 1986 FSAR Section Section 14.2.10 (page 14.2-10):
This change clarifies that the Red Control Cluster Assemblies need not be verified in proper location by RCCA ID number since for initial fuel loading all RCCAs have no fluence.
Safety Evaluation: The RCCAs will function as required regardless of core location. The RCCA and rod drop times are not affected by any particular RCCA pattern within the core locations provided with RCCAs. This change involves no unreviewed safety question.
Section 14.2.10.1 (page 14.2-11):
i This change specifies that all core locations which are designed to have
)
RCCA's are to be visually checked to ensure that this is the case.
Safety Evaluation:
This change ensures that the appropriate core loca-tions are provided with RCCA's. The change does not adversely affect j
plant safety and involves no unreviewed safety question.
j Table 14.2.7-1 (page 6):
This change clarifies that power coefficient measurements at 90% power will be performed only for Unit 1.
Unit 2 has essentially identical fuel and core loading as Unit 1.
Safety Evaluation: Errors between measured and predicted power coeffi-cients at 30%, 50%, 75%, and 90% on Unit I were less than the acceptance i
criterion value of i 0.5%.
There is no reason for Unit 2 measurements to be different from their predicted values. This change does not adversely affect plant safety and does not involve any unreviewed safety question.
Table 14.2.11-1:
This change is a correction to reflect the' proper start of Commercial Operation Date for Unit 2.
Safety Evaluation: This correction has no imlact on plant safety. This correction to historical data does not involve any unreviewed safety question.
I 4
2 of~4 Table 14.2.12-1 (page 21):
This change clarifies that the limiting mode for non essential flow is shutdown with blackout. This is a more restrictive condition that previously indicated.
Safety Evaluation: This change specifies more restrictive testing condi-tions. The change has no adverse impact on safety and does not involve any unreviewed safety question.
Table 14.2.12-1 (page 22):
This change to the test abstract removes a possible source of confusion by eliminating numerical references to modes of operation for the Nuclear Service Water System. Also, a reference to testing involving a shutdown with blackout was corrected to reflect the previous change to Table 14.2.12-1 (page 21).
Safety Evaluation: The first part of this change is administrative in nature. The second part of the change references more restrictive testing conditions than previously indicated. The change does not adversely impact safety and does not pose any unreviewed safety question.
Table 14.2.12-1 (page 22):
This change to the Acceptance Criteria clarifies and updates the criteria to be applied to the test. Acceptance criteria is provided by Design Engineering.
Safety Evaluation: This change does not adversely affect any safety related equipment, and it does not reduce any margin of safety. The change does not pose any unreviewed safety question.
Table 14.2.12-1 (page 48):
This change rewrote the test prerequisiter in the Piping System Vibration Test Purpose in order to clarify them. This basically is an editorial change.
Safety Evaluation: This editorial change does not affect the test in question, and it does not have an adverse impact on safety. This change does not pose any unreviewed safety question.
Table 14.2.12-2 (page 12):
This change to the Initial Criticality Test Method replaces the approxi-mate point at which dilution is stopped with a more conservation valve.
Safety Evaluation: This is a conservative change to provide for a con-trolled approach to criticality.
The change does not adversely affect safety, and it does not involve any unreviewed safety question.
3 of 4 Table 14.2.12-2 (page 14):
This change to the Zero Power Physics Test Acceptance Criteria allows Duke Power to apply criterion provided by Westinghouse to the Controlling Pro-cedure for Zero Power Physics Testing.
Safety Evaluation: This change is consistent with Technical Specifica-tions and assumptions made in the FSAR Chapter 15 Accident Analyses.
Plant safety.is not affected. The change does not involve any unreviewed l
safety question.
Table 14.2.12-2 (page 22):
This change to the Doppler Only Power Coefficient Verification clarifies that the test was to be performed on Unit 1 only, i
Safety Evaluation:
Since Unit I and Unit 2 have essentially identical core designs, both measured and predicted Doppler coefficients are almost i
identical. Doppler coefficients calculated for Unit 2 are therefore within the margin defined by the FSAR accident analyses. This change involves no adverse effect to safety, and it does not pose any unreviewed safety question.
Table 14.2.12-2 (page 33):
This change to the Natural Circulation Verification Test clarifies that the test was to be performed for Unit 1 only.
Safety Analysis: Unit 2 design is very similar to Unit 1 design. Since the test objectives have already been demonstrated for Unit 1, there is no need to repeat the test. This change does not adversely affect safety, and it does not involve any unreviewed safety question.
Figure 14.2.11-1 (Zero Power Physics Testing):
These changes to the Testing Following Initial Fuel Loading Figure specify that the Integral Control Rod Worth With one Stuck Rod Test and the Pseudo-Ejected RCCA Worth at Hot Zero Power were to be performed on Unit I only.
Safety Evaluation:
This change brings figure 14.2.11-1 in agreement with the Zero Power Physics Test description in Table 14.2.12-2.
Thus this change is administrative in nature and does not involve any unreviewed safety question.
j Figure 14.2.11-1 (Post-Physics Testing):
This change clarifies that the Natural Circulation Verification is to be performed for Unit 1 only.
Safety Evaluation: This change brings the affected section of Figure 14.2.11-1 in agreement with the change to Table 14.2.12-2 (page 33) previously described in this report. As previously indicated, the change does not adversely affect safety, and it does not involve any unreviewed safety question.
I 4 of 4 Figure 14.2.11-1 (10-25% Power Testing):
This change adds requirements to perform the Nuclear Instrumentation Initial Calibration and the Steam Generator Water Hammer Test at this power level.
Safety Evaluation:
This change added testing requirements to Figure 14.2.11-1.
The subject tests are already described in Table 14.2.12-2.
Therefore, this change is administrative in nature and does not pose any unreviewed safety question.
)
1 Figure 14.2.11-1 (~30% Power Level Testing):
These changes clarify that the Psuedo Ejection Rod Test and Doppler only Power Coefficient Verification were to be performed for Unit 1 only.
Also, the Steam Generator Water Hammer Test was eliminated at this power level.
Safety Evaluation:
These changes bring Figure 14.2.11-1 in agreement with the respective Sections of Table 14.2.12-2 or reflect changes previously justified in this report. Therefore, these changes are of an administra-tive nature and do not involve any unreviewed safety question.
Figure 14.2.11-1 (~50% Power Level Testing):
These changes clarify that the Doppler only Power Coefficient Verification and the Below Bank Test were to be performed on Unit 1 only.
Safety Evaluation: These changes bring Figure 14.2.11-1 in conformance with Table 14.2.12-2 or with changes previously justified in this report and are therefore of an administrative nature. These changes do not involve any unreviewed safety question.
Figure 14.2.11-1 (~75% Power Level):
This change clarifies that the Doppler only Power Coefficient Verification at this power level was to be performed on Unit 1 only.
Safety Evaluation: This change to Figure 14.2.11-1 reflects changes previously justified in this report.
This change is therefore admini-strative in nature and does not involve any unreviewed safety question.
Figure 14.2.11-1 (~90% Power Level Testing):
1 These changes clarify that the Feedwater Temperature Verification Test and the Doppler only Power Coefficient Verification were to be performed on Unit 1 only.
Safety Evaluation:
These changes bring Figure 14.2.11-1 in conformance with the applicable Sections of Table 14.2.12-2 or reflect changes previ-ously justified in this report. These are administrative changes which do not involve any unreviewed safety question.
)
1 1 of 19 CATAWBA NUCLEAR STATION Summary of Nuclear Station Modifications and j
Exempt Change Variation Notices Completed Under j
10CFR50.59 During 1986 1
CN10005
Description:
This Unit 1 modification provided for the replacement of previously installed flow switches on the appropriate process radiation monitors with a more suitable model. The new flow switches have a larger, more open interior design which has proven less susceptible to clogging problems as demonstrated by its use at McGuire Nuclear Sta-tion.
This modification affects FSAR Figures 9.3.5-5, 11.2.2-3, 11.2.2-11, 11.2.2-12, 11.3.2-2, 9.3.2-1, 9.3.2-5, 9.2.2-1, 9.2.1-5, and 9.2.1-9.
Safety Evaluation: No safety system was degraded an no func-tional change to any system was made as a result of this modification. This modification does not involve any unre-viewed safety question.
CN-10049
==
Description:==
This Unit 1 modification provides an 8 inch line from the steam jet air ejector exhaust line to the gland seal condenser exhaust line on the auxiliary building roof.
Valves are provided to direct the air ejector exhaust to the unit vent whenever the Auxiliary Building Ventilation (VA) System is unable to receive air ejector discharge due to malfunction-ing or contaminated exhaust air.
This modification affects FSAR Figure 10.4.2-1 and 10.4.3-2.
Safety Evaluation: This modification provides capability to route the air ejector discharge to the unit vent if the condenser off gas has radioactive contamination to limit its spread to the office areas.
This modification is not safety related and does not pose any unreviewed safety question.
CN-10078
==
Description:==
Previous pressure regulators on the conventional sample lines for Unit 1 Steam Generators 1A, IB, IC, 1D, Final Feedwater Heater, Hotwell Discharge, Polish Demineralizer Main Effluent, and Heater Drains (1C1 and IC2) were replaced with regulators capable of providing higher pressure and flow.
The pressure relief valves were also re-set to accommodate the new regulators. This modification affects FSAR Figures 9.3.2-6, 9.3.2-7, and 9.3.2-8.
Safety Analysis: No safety system was degraded and no func-tional changes were made to any system as the result of this modification. The replacement regulators allow for adequate flow and pressure to keep all the analyzers in operation simultaneously. No unreviewed safety question is posed by this modification.
2 of 19 1
CN-10089 This modification provided for the replacement of Unit I relief valves 1NM 67, 255, 256, 257, and 258 in the Nuclear Sampling System (NM) with bypass check lines. This modification was implemented because potential problems experienced at McGuire Nuclear Station (MNS) due to these safety-relief valves lifting due to water hammer when sampling'is started or 2
stopped.
This modification affects FSAR Table 6.2.4-1 and Figures 5.1-1, 5.1-2, 9.3.2-1, 9.3.2-5, and 11.2.2-14.
Safety Evaluation: This modification eliminates potential problems identified at MNS. No safety system was degraded and no functional change to any system was made as a result of implementation of this modification. This modification does not involve any unreviewed safety question.
l CN-10090
==
Description:==
This Unit 1 modification replaced approximately 2
9,000 ft of sidewall fixed louvers with air operated movable louvers in the Turbine Building. This modification was implemented to provide freeze protection by closing the louvers in cold weather. This modification affects FSAR Figure 9.4.7-1.
Safety Evaluation: This modification does not degrade any 1
safety system or make any change to any system. No unre-viewed safety question was involved or created with the implementation of this modification.
CN-10116
==
Description:==
This modification replaced an earlier temporary Unit I system installed for treating the Component Cooling (KC) Water with a corrosion inhibitor. One chemical feeder is added to each train (A&B) of the Unit 1 KC-System. This modification affects the FSAR Figure 9.2.2-1.
Safety Evaluation: This modification replaces some temporary chemical feeder equipment with permanent chemical treatment equipment in the Component Cooling System. There is no degradation or functional change of any Safety System due to this modification. The new equipment' installed does not have a safety related function. This modification does not pose any unreviewed safety question.
CN-10118
==
Description:==
This modification provided for the replacement of Unit 1 valves 1RN289, 1RN288, 1RN145, 1RN853, 1RN349, 1RN348, 1RN226, and 1RN852 in the Nuclear Service Water System (RN).. This modification was implemented because the previous-ly installed valves had small openings which could clog easily.
This modification affects FSAR Figures 9.2.1-5, 9.2.1-6, 9.2.1-9, and 9.2.1-10.
Safety Evaluation: This modification improves system reliabil-ity. No safety system was degraded and no functional change was made to any system with the implementation of this modifi-cation. This modification does not involve any unreviewed l
safety question.
3 of 19 i
i CN-10121
==
Description:==
This modification provides-a station outside the i
Unit 1 pump rooms where the nitrogen charge on the reciprocat-ing charging pumps suction and discharge dampeners can be checked and replenished as required without having to enter the room. This modification was performed to keep radiation doses ALARA since the pump room is a high radiation area.
Safety Evaluation: This modification involves no functional change, and no safety system is degraded as a result of this modification. The modification does not pose any unreviewed safety question.
CN-10164
==
Description:==
This aodification installed flexible reach rods to Unit 1 valves IWI43,1WLA55,1WLA59,1WLA66,1WLA72, 1WLA83, 1WLO49, IWLO52, iFL151, 1WL158, IWL202, IWL253, IWL290, 1WL312, 1WL338, 1WL344, 1WL369, 1WL923, 1WL953, 1WL990, 1WL991, 1WL992 and 1WL996 of the Liquid Radwaste (WL)
System. This modification also installs handwheels outside the rooms where the valves are located in high radiation areas to minimize radiological exposure of personnel. This modifi-cation affects FSAR Figures 11.2.2-3,
-4, -5,
-6 and -7 of the WL system.
I Safety Evaluation: This ALARA modification enhances personnel I
safety by installing equipment which would reduce personnel exposure to high radiation fields. This modification does not pose any unreviewed safety question.
CN-10210
==
Description:==
This modification provided for the upgrading of the outside containment portion of the Incore Thermocouples to Class IE and for the addition of Class 1E Core Subcooling Margin Monitoring Capability.
In addition, the appropriate analog displays were replaced with graphic displays.
This modification affects FSAR Section 1.9.
Safety Evaluation: This modification provides instrumentation to monitor plant variables during and following an accident and is being implemented in response to Regulatory Guide 1.97 Revision 1, and NUREG 0737 Section 11.F.2.
The modification increases system reliability and no safety system will be degraded as a result of its implementation. This modification does not involve any unreviewed safety question.
CN-10238
==
Description:==
This modification installs a small heat exchang-er at the primary discharge drains for each loop (Auxiliary Building, Service Building and Unit 1 Turbine Building) in the Plant Heating System (YH).
This modification affects FSAR Figare 9.2.8-2.
Safety Evaluation:
The ethylene glycol in the YH system is too hot to sample safely and this modification is needed to provide some sample cooling capability.
This modification is not safety related and does not pose any unreviewed safety question.
4 of 19 i
CN-10239
==
Description:==
This modification provided for the installation of additional Unit 1 instrument root valves outside the shield wall and a reservoir vent line and valve for each pressurizer pressure and level instrument loop. The root valves located in the pressurizer cavity were extremely difficult to access.
Safety Evaluation: This modification assures that leaking valves or fittings can be isolated and repaired without a l
forced outage or conditions posing some personnel safety concerns. This modification does not degrade any safety system or result in any functional change of any system. This modification does not pose any unreviewed safety question.
CN-10268
==
Description:==
This modification provided for the installation of an 8 inch line connecting the Unit 1A and B Component Cooling System surge tanks. This line allows a flow of 3,000 to 5,000 gallons per minute between each tank and is connected at the top of each tank.
This modification affects FSAR Section 9.2.2 and Figure 9.2.2-2.
Safety Analysis: This modification provides surge tank overflow protection and increases system reliability. No safety system is degraded and no functional change is made as a result of the modification.
This modification does not l
involve any unreviewed safety question.
CN-10323
==
Description:==
This modification provided for the installation of temperature elements upstream of Unit 1 check valves ICA41, 45, 49, 53, 57, and 61.
Some electrical work was also re-quired to provide the computer with the appropriate signals and for the computer to indicate the temperatures and provide the desired alarms on increasing temperature indicating backleakage through the check valves. This modification affects FSAR Figure 10.4.9-2.
Safety Evaluation: This modification is intended to aid in the prevention of backleakage of hot feedwater into low pressure portions of a normally nonoperating Auxiliary Feed-water System (which could result in steam void formation disabling the System). The modification does not adversely affect any system or cause any functional change to take place as a result. No unreviewed safety question is created or involved as a result of this modification.
j l
CN-10333
==
Description:==
This modification provided improvements to reduce fuel oil spills at the Unit 1 oil fill line filter area.
The fuel oil is considered a hazardous waste in South Carolina and oil spills require costly clean up.
This modifi-cation lowers the fuel oil line filter so that the inlet and outlet connections of the filter are below the fuel truck l
discharge connection thus preventing spillage of oil during disconnecting of the oil filling hose. Also a small " rolled curb" area is provided around the fuel oil fill line filter
5 of 19 base to contain inadvertent spills. This modification affects FSAR Figures 9.5.4-1 and 9.5.4-2.
Safety Evaluation: This modification is not safety related and does not pose any unreviewed safety question.
CN-10338
==
Description:==
This modification provided for the upgrading (Class C) and rerouting of the Unit 1 Refueling Water Storage Tank (FWST) overflow line to the Unit 1 Spent Fuel Pool instead of the Waste Evaporator Feed Tank (WEFT) to adequately handle overflow of the FWST.
A flow switch was also added to the overflow line that alarms the computer on FWST overflow.
This modification affects FSAR Figures 9.1.3-1, 9.2.7-1, and 11.2.2-5.
1 Safety Analysis: This modification eliminated one possible overflow source to the WEFT and reduced the possibility of a spill on the 543' elevation.
This contributes towards reducing radiation exposure ALARA.
This modification does not involve any unreviewed safety questions.
CN-10355
==
Description:==
This modification provides additional essential power source to each Unit I process protection sets (I, II, III and IV in Power Panel Boards).
A separate feeder is provided for each cabinet internal power supply.
1 Safety Evaluation: This modification provides additional feeder supply needed to prevent a single power supply compo-nent from tripping the feeder breaker and disabling the backup power supply.
This modification improves reliability by correcting a design deficiency. This modification does not degrade any safety system or results in any funct.ional change to any system. This modification does not pose any unreviewed safety question.
CN-10360
==
Description:==
This modification provides permanent wiring for the themocouples installed on the exhaust manifold of the diesel generators to monitor the preturbo charger exhaust gases temperature and the monitor chart recorder (Unit 1).
Safety Evaluation: This modification is made in response to.
an NRC request and provides diesel generator reliability data.
This modification does not pose any unreviewed safety question.
CN-10367
==
Description:==
This modification provides temperature monitor-ing capability for the Unit 1 diesel generator exhaust gases.
This modification is being made pursuant to an NRC commitment.
Safety Evaluation:
Installation of thermocouples in_the exhaust manifold provides adequate temperature monitoring for the diesel generator exhaust gases.
This modification does not affect any safety related system or function adversely and does not pose any unreviewed safety question.
6 of 19 CN-10423
==
Description:==
This modification replaces Unit 1 Valve 1FW77 from the Refueling Water System (FW) with a short section of pipe. This valve is not required during normal operation and can potentially overpressurize the FW piping if inadvertently closed.
This valve is not required for isolation or any safety related function. This modification affects FSAR 1
Figure 9.2.7-1 of the Refueling Water System.
Safety Evaluation: This modification does not degrade any safety related system or adversely affect any safety related function. This mod'.fication does not pose any unreviewed safety question.
CN-10436
==
Description:==
.'is modification replaced 3/4" tubing and flex hose connected to Unit 1 PORV actuators with 1" tubing and flex hose. The revised instrument air connections to the valves INC 32B, 34A, and 36B improve the PORV respotse time.
This modification affects FSAR Figure 5.1-2.
Safety Evaluation: The Low Temperature Overpressure Protec-tion (LTOP) analysis assumes that the PORV response time to be 3
less than 3 seconds.
This modification assures that the PORV l
response times would be less than that assumed in the LTOP analysis presented to the NRC. This modification does not adversely affect any system.
Improved air supply to the PORV actuators is expected to enhance the reliability of the PORV's.
This modification does not pose any unreviewed safety question.
CN-10442
==
Description:==
This modification changed the failure response of the Unit I valves 1KC122 and 1KC128 from fail close to fail open to prevent a postulated event that could cause over pre-ssurization of the Component Cooling System (KC) surge tanks.
This modification affects FSAR Section 9.2.2 and Figure l
9.2.2-2.
Safety Evaluation: This modification is necessary to prevent a tube rupture from injecting high pressure radioactive water into the KC System and overpressurizing the surge tanks upon the closure of the KC surge tank vent valves. No safety system is degraded and no functional change is made to any system as a result of this modification. This modification does not involve any unreviewed safety question.
CN-10457
==
Description:==
This Unit 1 modification provides a 3 inch recirculation line and isolation valve downstream of the clean lube oil transfer filter back to the clean lube oil storage tank.
This modification assures that oil is recir-culated to provide a representative sample. This modification affects FSAR Section 9.5.7.2-1.
Safety Evaluation: This modification assures the capability of obtaining a representative lube oil sample.
Sampling of the lube oil is an FSAR requirement. This modification is not
7 of 19 safety related and does not adversely affect any safety system. This modification does not pose any unreviewed safety question.
CN-10463
==
Description:==
This modification provided for the addition of a high flow alarm to flow transmitters IKC FT 5530 and 5540 in the Component Cooling System (KC). The modification also pro-vides the logic to open valves 1KC 56A and 81B and to close valves IKC 230A, 3A, 228B, and 18B upon Low Refueling Water Storage Tank level following an "S" signal or upon generation of a "P" signal.
This modification prevents runout of one train of KC pumps following failure of the other train.
Safety Evaluation:.This modification improves system reli-ability. The modification does not adversely impact any safety or non-safety system and no unreviewed safety question is involved.
CN-10476
==
Description:==
This modification provided for the upgrading of the piping between Unit I valves 1NC 224 and INC 225 of.the Reactor Coolant System to Pipe Specification 2501.4. This sec-tion of the pipe could have become inadvertently pressurized and posed some personnel safety concern.
Sight glass INCGF 6230 was also replaced with a new instrument qualified up to 2500 psia and 300 F service conditions. Valve INC 225 was designated locked open to prevent the possibility of overpressurization of the pipe section involved (FSAR Figure 5.1-2).
Safety Evaluation: The replacement of a section of pipe and sight glass by a pipe and sight glass qualified for higher QA standards does not adversely affect any safety system structure or component.
This modification does not pose any unreviewed safety question.
i 1
CN-10505
==
Description:==
This modification provided for the installation of strainers on the inlet to the Unit 1 lube oil pressure i
regulating valves ILD4, ILD24, ILD34 and ILD57 to prevent any collection of debris in the valves and adversely affecting their performance.
This modification affects FSAR Figure 9.3.1-4.
Safety Evaluation: This modification improves the reliability of the Lube Oil System for the diesel generators and reduced the amount of preventive maintenance required for the Lube Oil pressure regulating valves. This modification is not safety related and does not affect safety related portions of the diesel generators and associated systems. This modification does not pose any unreviewed safety. question.
CN-10522
==
Description:==
This modification resulted in the installation of a new Unit I system that provides:
- 1) Post-accident neutron flux instrumentation (as required "by Regulatory Guide 1.97); and 2) Automatic mitigation of the consequences of a i
8 of 19 Boron Dilution Accident (as required by Regulatory Guide 1.70 and the Standard Review Plan Section 15.4.6); and 3) Source Range neutron flux instrumentation in the Standby Shutdown Facility (SSF) (as required by 10CFR50 Appendix R); and 4)
Neutron Flux indication on the Auxiliary Shutdown Panel (ASP).
I This modificatien affects FSAR Sections 7.5 and 15.4.
I Safety Analysis: This modification was required to satisfy Licensing commitments for post-accident monitoring and SSF, ASP monitoring, as well as boron dilution mitigation. The modification does not adversely affect any safety or non-safety system, or involve any unreviewed safety question.
CN-10523
==
Description:==
The modification. upgrades the Unit 1 Pressurizer Power Operated Relief Valve (PORV) control systems (both air and electrical) to safety grade. The PORVs INC34A and INC32B are provided with safety grade sources of compressed Nitrogen from cold leg accumulators CLA1A.and CLAIB respectively.
This modification affects FSAR Figure 9.3.1-2 and FSAR Section 5.1 and 6.3.2-2.
Safety Evaluation: This modification upgrades a control grade system associated with PORV's to safety grade enhancing safety and reliability. This modification is required to provide Low Temperature Overpressure Protection (LTOP) in accordance with Catawba License condition #18.
This modification does not adversely affect any safety related system or function. This modification does not pose any unreviewed safety question.
CN-10524
==
Description:==
This modification provided for the upgrade of the Unit 1 Steam Generator (SG) Power Operated Relief Valves (PORVs) to safety grade. This modification affects FSAR Section 10.3.2 and Figure 10.3.2-1.
Safety Evaluation: This modification resulted in an upgrade of the subject system. No other system was degraded as a result of this modification.
This modification was required by License Condition No. 18 and does not involve any unreviewed safety question.
CN-10526
==
Description:==
This modification reassigned power to the Unit 1 diesel generator monitoring circuits in the control room to a non-interruptible panelboard (1KXPA) to provide a highly reliable source of power. The previous arrangement results in loss of power to the diesel generator monitoring circuits during a station blackout testing.
Safety Evaluation: The diesel generator monitoring circuits are not safety related.
This modification does not adversely affect any safety system or make any functional change in any system. This modification provides highly reliable lower to the diesel generator monitoring circuits and does not pose any unreviewed safety question.
1 9 of 19 CN-10570
==
Description:==
This Unit 1 modification relocates valve INM411 upstream of the flow orifice and downstream of valve INM13 and valve INM418 upstream of flow orifice and downstream of INM418.
This modification also rebores the 4 flow orifices with 3/64" diameter bore.
These modifications are necessary to ensure that the reactor coolant samples can properly drain through the orifices at atmospheric pressure as required for proper functioning of the Nuclear Sampling System. This modification affects FSAR Figure 9.3.2-1.
j 1
Safety Evaluation: This modification removes a design defi-ciency which prevents operators from obtaining reactor coolant samples in an efficient manner. This modification does not degrade any safety system and does not result in a functional
{
change in any system _.
This modification does not pose any unreviewed safety question.
CN-10582
==
Description:==
This modification provided for the installation of additional support / restraints to the Unit 1 Diesel Genera-tor (D/G) 1A and IB starting air manifolds. This modification was recommended by the NRC.
Safety Analysis: This modification does not degrade any safety system or result in any functional change to any system. The modification does not involve any unreviewed safety question.
CN-10585
==
Description:==
This modification provided for the installation of additional support / restraints on the Unit 1 fuel oil headers on D/G 1A and IB.
This modification was made in response to an NRC request.
Safety Evaluation: This modification involves no functional change of any system. Additional support / restraints result in increased system reliability and do not adversely affect any j
safety or non-safety system.
The modification does not
)
involve any unreviewed safety question.
CN-10601
==
Description:==
This modification provided for the addition of j
the required block valver and a drain valve to the Unit 1 Component Cooling System (KC)_to permit Type C leak rate testing on valve 1KC279.
This modification affects FSAR Figure 9.2.2-4.
Safety Evaluation: This modification allows for Type C leak rate testing to be performed on valve 1KC279. This modifica-tion does not degrade any safety system, and no functional changes are made to any system. The modification does not involve any unreviewed safety question.
CN-10609
==
Description:==
This modification provided for the addition of a local control at the Auxiliary Shutdown Panel (ASP) to allow throttling of Unit 1 valve INV294 (Ch-mical and Volume Control System Pump Discharge Flow Control Valve).
The modification
10 of 19 is required because when control is transferred to the ASP, INV294 fails open causing a. rapid decrease in Volume Control Tank level and a rapid increase in Pressurizer Level. At this point, immediate operator action is required to throttle a local gate valve in line with INV294 which made it difficult and time consuming to achieve the desired flow. The modifica-tion affects FSAR Table 7.4.7-1 and Figure 9.3.4-8.
Safety Evaluation: This modification allows for the proper throttling of valve INV294 when required and no safety system is degraded as a result of this modification.
This modifica-tion does not involve any unreviewed safety question.
CN-10620
==
Description:==
This modification provided for the installation of an ennunciator at the Unit 1 1A and IB diesel engine control panel to alert control room of loss of D.C. control power. Actuation of the control panel annunciator window will cause activation of the " diesel generator trouble" summary annunciator window in the control room (as will any local i
panel alarms).
Safety Evaluation: This modification does not degrade or cause a functional change in any system, and it does not pose any unreviewed safety question.
CN-10837
==
Description:==
This modification provided for the replacement and rerouting of piping on the Unit 1 Water Jacket System of Diesel Generators IA and 1B with Duke Class C piping. The previously installed piping did not allow for proper thermal
{
expansion during operation. This modification affects FSAR Figure 9.9.5-1.
Safety Evaluation: This modification corrected a situation
)
where piping did not allow for the appropriate thermal expansion. This modification meets or exceeds the design standards of the previously installed vendor piping and does not pose any unreviewed safety questions.
CN-10865
==
Description:==
This modification provided for the installation of a Unit 1 Sulphur Hexafloride Condenser tube leak detection system to identify the waterbox containing the leaking tubes.
The previously installed leak detection system did not accu-rately identify the faulty waterbox and required draining and isolation of waterboxes to identify the waterbox containing, i
the faulty tubes.
Safety Evaluation: This modification does not affect any j
safety related system, structure, or component and does not j
pose any unreviewed safety question.
CN-10884
==
Description:==
This modification provides for the installation of additional 1-10 SCFM range Rotometers in parallel with existing Unit 1 instrumentation on the discharge side of each Condenser Steam Air Ejector (CSAE) so that accurate off-gas j
l l
11 of 19 readings can be obtained at low flow. This inodification affects FSAR Figure 10.4.2-1.
Safety Evaluation: This modification was implemented to allow for accurate off-gas measurements under low flow conditions to determine if air intake into the condenser is within accept-able limits. This modification improves system reliability and does not adversely affect any system. This modification does not involve any unreviewed safety question.
CN-10896
==
Description:==
This modification provided personnel access to the Unit i ventilation room access ladder located at 180 azimuth on elevation 552' by modifying the recirculation sump screen doors. The modified sump screen doors provide a two feet wide walkway through the sump screen area next to the crane wall.
The previous access route required crawling through an area on the side of the filter gates close to the annulus wall. This route was dangerous and unsuitable.
Safety Evaluation:
This modification alleviates a personnel hazard potential by providing a suitable access to the venti-lation room on elevation 552'.
The modification does not degrade or make any functional changes in the sump screens.
This modification does not pose any unreviewed safety question.
CN-10979
==
Description:==
This modification provided for the increase of the Unit 2 turbine driven Auxiliary Feedwater Pump governor setting from 3,600 up to 3,800 revolutions _per minute (RPM).
This modification affects FSAR Table 10.4.9-2.
Safety Evaluation:
This modification was required in order to obtain the appropriate head and flow conditions. This modifi-cation was evaluated by the NRC and found to be appropriate (letter from Thomas M. Novak (NRC) to Hal B. Tucker (DPCo) dated November 13, 1986).
This modification does not involve any unreviewed safety question.
CN-20072
==
Description:==
This modification provides control room annun-ciation upon loss of input or output power for each of.the two Unit 2 Solid State Protection Systems (SSPS). Also local
" Power On" indication is provided on each SSPS input cabinet door (4 per SSPS).
Safety Evaluation:
This modification eliminates the potential of an undetected failure of power supply to the SSPS cabinets.
This modification does not degrade any safety system or result in a functional change to any system. This modification does not pose any unreviewed safety question.
CN-20084
==
Description:==
This modification provides a control scheme to,.
reduce Unit 2 feedwater pump speed to minimum setting on a reactor trip. The previous feedwater tripaon low T-average has led to overpressurization of the high pressure feedwater
12 of 19 heaters after reactor trip.
The high pressure feedwater heater relief valves have been regularly challenged and have 3
caused damage to the heater in event of relief a valve failure.
J Safety Evaluation: This modification provides a main feed-water pump trip on safety injection or Hi-Hi steam generator water level. Also a signal is added to the main feedwater pump turbine (CFPT) speed control circuit to run back its speed to the low speed setting when the reactor trips. This trip is not safety related and this modification does not pose any unreviewed safety question.
CN-20194
==
Description:==
This modification provided for the installation of a flow transmitter (2NVFT6270) across the Unit 2 Borono-I meter output test connections with a receiver gage outside the Boronometer room to facilitate taking Boronometer output flow measurements without entering the high radiation area in i
the Boronometer room. This modification affects FSAR Figure 9.3.4.7.
Safety Evaluation: This modification provides a remote indication of the Boronometer flow measurement while maintain-ing radiation exposure ALARA.
The installation of the remote indication conforms to the QA Standard I for the safety grade instrumentation. This modification does not compromise the Boronometer function or the integrity of any process piping and does not pose any unreviewed safety question.
CN-20199
==
Description:==
This modification provides for the installation of a small sample heat exchanger at the Primary pump discharge for the Unit 2 Turbine Building loop of the Plant Heating System (YH). This change was implemented because the ethylene glycol in the YH system was too hot to be sampled safely.
This modification affects FSAR Figure 9.2.8-2.
Safety Evaluation: This modification provides cooling for ethylene glycol in the YH system to acceptable sampling j
temperatures, and it does not adversely affect any safety or non-safety system. The modification does not involve any 1
unreviewed safety question.
j CN-20217
==
Description:==
This modification provided for the upgrade of the power supply and controls for the Unit 2 Motor Operated Steam Generator Power Operated Relief Valves (PORV) Block j
Valves to Quality Assurance condition 1 power. This modifica-tion affects FSAR section 10.3.3.
Safety Evaluation: This modification upgraded Steam Generator PORV block valve power supplies and controls, and it does not adversely impact any safety or non-safety system.
This modification does not involve any unreviewed safety question.
CN-20276
==
Description:==
This modification installs additional Rotometers (range 1-10 SCFM) in parallel with existing Unit 2 instruments
13 of 19 on the discharge side of each Condenser Steam Air Ejector (CSAE).
Present instrument has a range of 6-70 SCFM and off-gas readings at low flow cannot be measured accurately.
1 Accurate off-gas measurements under low flow conditions are J
required to determine if the air inleakage into the condenser is within acceptable limits.
The modification affects FSAR Figure 10.4.2-1.
Safety Evaluation: This modification is not safety related and it does not pose any unreviewed safety question.
CN-20282
==
Description:==
This modification provides access from the Unit 2 pipe chase area at 180 azimuth (Elevation, 552' + 0) to 270 azimuth. The recirculation sump screen doors cannot be used to move from the pipe chase area since the Technicel Specifi-cations require operability of one train of the sump at all times. This modification provides a 2-foot walkway through the sump screen area next to the crane wall to provide personnel access.
Safety Evaluation: This modification provides a safe person-nel access through the sump screen area as recommended by a design engineering study. This modification does not change the usable volume of the sump or the screen surface area significantly.
This modification does not change any safety function or pose any unreviewed safety question.
CN-20340
==
Description:==
This modification provides all the necessary electrical changes in the Unit 2 Main Generator Isolated Phase Bus and Protective Relaying Systems to accommodate the instal-lation of a new double ended replacement generator stator supplied by General Electric.
Safety Evaluation: This modification is.not safety-related and does not directly or indirectly involve any plant safety function. The only FSAR accident analysis related to the generator is FSAR Section 15.2.2, " Loss of External Load".
This modification does not increase the likelihood of such an accident, and it does not pose any unreviewed safety question.
CN-20369
==
Description:==
This modification provided for the increase of the Units 1 and 2 turbine driven Auxiliary Feedwater Pumps governor settings from 3,600 to 3,800 revolutions per minute (RPM). This modification affects FSAR Table 10.4.9-2.
Safety Evaluation: This modification was required in order to obtain the appropriate head and flow conditions.
This modifi-cation was evaluated by the NRC and found to be appropriate (letter from Thomas M. Novak (NRC) to Hal B. Tucker (DPCo) dated November 13, 1986). This modification does not pose any unreviewed safety question.
14 of 19 I
l CN-50005
==
Description:==
This modification provided for the installation of flash mixers in the waste Monitor Tanks A and B, Floor Drain Tank, laundry and Hot Shower Tank, and the Waste Evapo-rator Feed Tank to prevent sludge accumulation and buildup.
This modification is shared by both Units and affects FSAR Figures 11.2.2-3, 11.2.2-4, 11.2.2-5, and 11.2.2-9A.
Safety Evaluation: This modification is part of a radwaste system upgrade and it enhances the system reliability while i
reducing ALARA concerns.
The modification does not adversely impact any safety or non-safety system, and it does not
)
involve any unreviewed safety question.
)
i CN-50006
==
Description:==
This modification provided for the installation of a Floor Drain Leak Detection System in the Auxiliary Building in order to monitor for leaks of radioactive liquids and to reduce exposure (ALARA).
This modification also provides a response to commitment s in NUREG 0978, Section 2.1.6a, Regulatory Guide 8.8, Section C4.h, and Regulat( ry Guide 8.10, Section C.1.f.
This modification affects both i
Units.
)
Safety Evaluation: This modification reduces personnel j
exposure (ALARA). No safety system was degraded and no functional change was made to any system as a result of this modification.
This modification does not involve any unre-viewed safety question.
CN-50013
==
Description:==
This modification added previsions to prevent the entry of live asiatic clam larvae into the Fire Protection System (RF) piping. The modification is shared by both Units and it affects FSAR Section 2.2.3 and Figure 9.5.1-1.
Safety Evaluation: Clam larvae injected into the RF system after a main fire pump start can grow within the system and render portions of the system inoperable. This modification prevents the injection of live larvae and eliminates the uncertainties associated with the effectiveness of the purge method previously used to eliminate larvae from the system.
This modification does not adversely affect any system or j
involve any unreviewed safety question, i
CN-50033
==
Description:==
This modification installs flexible reach rods and locates handwheels outside rooms for several valves in the Boron Recycle (NB) System. This modification is needed due to l
valves being located in rooms which are difficult to access due to hangers or high radiation dose fields. This modifica-tion is shared by both Units and affects FSAR Figures 9.3.5-3 and 9.3.5-6.
Safety Evaluation:
This modification enhances personnel j
safety and does not pose unreviewed safety question.
i
15 of 19 CN-50063
==
Description:==
This modification routes the sink and dichwater drains from the Cold Lab to the floor drain tank Sump C.
This-modification is shared by both Units and affects FSAR Figures 11.2.2-3 and 11.2.2-4.
Safety Evaluation: This modification prevents the non-con-taminated water to be drained to the radwaste processing system.
This modification is not safety related and does not pose any unreviewed safety question.
CN-50071
==
Description:==
This modification involved the installation of a 3/4" stainless steel pipe from the Waste Gas Compressor to the floor drain in the respective compressor rooms. An isolation valve was also located in each line to provide easy access for maintenance. The modification is shared by both Units and affects FSAR Figures 11.2.2-1 and 11.3.2-1.
Safety Evaluation:
Implementation of the modification did not result in any functional changes to any system and no system was adversely affected.
This modification does not involve
)
any unreviewed safety question.
CN-50072
==
Description:==
This modification installs the necessary piping, valves and ather components to process liquid waste through the vendor supplied demineralizers. This modification would greatly reduca the need to evaporate a large amount of liquid radwaste.
Tuis modification affects FSAR Figures 9.3.5-3, 9.3.5-5, 11.2.2-2, 11.2.2-3, 11.2.2-4, and 11.2.2-5.
Safety Lynluation: This modification reduces the need to evaporace a large amount of liquid radwaste on site and instead uses cost effective vendor supplied equipment.
This modifier. tion is not safety related.
This modification does not pose any unreviewed safety question.
CN-50087
==
Description:==
This modification provided for the relocation of the Liquid Waste System (WL) Waste Evaporator Eductor from its previous location to the Evaporator Skid level. Also, Eductor discharge was increased from 1" to 2".
This modification was implemented because when feedwater was put through the Eductor, backflow into the vent condenser caused flooding of the component. This modification is shared by both Units and affects FSAR Figures 11.2.2-5 and 11.2.2-6.
Safety Evaluation: This modification constitutes an upgrade of the system and does not adversely impact any safety or non-safety system. The modification does not involve any i
unreviewed safety question.
JN-%088
==
Description:==
This modification provided for the installation of the appropriate pressure gauges on the suction lines of affected Chempumps in the Refueling Water System (FW), Boron Recycle System (NB), Liquid Waste Recycle System (WL), Nuclear a
i 16 of 19 j
l Solid Waste Disposal System (WS), and Gaseous Waste Management System (WG). A discharge gauge was also installed on the Waste Gas Decay Tank Drain Pump.
Implementation of this modification was required to properly determine pump perfor-mance and system conditions. This modification is shared by both Units and affects FSAR Figures 9.3.5-3, 9.3.5-6, j
11.2.2-4, 11.2.2-5, and 11.3.2-4.
Safety Evaluation: This modification improves system reli-ability, and it does not adversely affect any safety system.
No functional change was made to any system as a result of the modification. This modification does not involve any unre-viewed safety questioni CN-50109
==
Description:==
This modification provided for the replacement j
of conductivity probes in thc Liquid Waste Recycle System (WL)
Evaporator Condensate Return Tank and in the Boron Recycle (NB) Evaporator Condensate Return Tank with differential pressure transmitters. The modification is shared by both Units, and it affects FSAR Figures 9.3.2-5 and 11.2.2-6.
Safety Evaluation: This modification was implemented because previous conductivity probes were incapable of accurately determining the water levels due to high purity of the conden-sate. This modification does not adversely affect any system and no unreviewed safety question is involved.
CN-50128
==
Description:==
This modification provided for the removal of a vertical loop which was inadvertently designed into the suction piping of the Spent Resin Sluice Pump.
Pre-operation-al testing has shown that the loop trapped air and caused a loss of proper pump suction conditions during sluicing.
The piping was straightened to-prevert trapping of air. Also, valve IWS 20 (located in the Nucleac Solid Waste Disposal System) had its leak off piped to a local drain. This modifi--
cation is shared by both Units and affects FSAR Figures 11.2.2-1 and 11.4.2-1.
l Safety Evaluation: This modification corrected a deficiency 1
identified during pre-operational testing. No safety system was degraded and no functional change took place as a result i
of this modification.
This modificatibn does not involve any unreviewed safety question.
1 CN-50139
==
Description:==
This modification provides a flow monitor upstream of the waste monitor tank (WMT) and flow totalization instrument between each tank nozzle and the first valve upstream. The range of the flow instrumentation is from 0 to 60 gpm and the totalization instrument has range up to 5500 gallons providing capability to monitor entire tank volume.
This modification affects FSAR Figure 11.2.2-9A and 11.2.2-4 of the Liquid Radwaste System and is shared by both Units.
Safety Evaluation: This modification provides flow monitoring capabilities to WT during processing. This modification does
1' 17 of 19 not degrade any safety related system or result in a function-al change in any system. This modification does not pose an unreviewed safety question.
CN-50151
==
Description:==
This modification provides redundant large capacity filters for the Liquid Waste Recycle System Floor Drain Tank (FDT), Laundry and Hot Shower Tank (LHST). The new filters meet the constraints imposed by the filter pits and spent filter cartridge removal scheme currently in use.
This modification affects FSAR Section 11.2.2.1 and Table 11.2.2-3.
Safety Evaluation: Present filters are inadequately sized and require an excessive number of cartridge replacement per active filter. The proposed modification would increase system availability without cartridge replacement. No safety system was degraded and no functional change was involved as a result of the implementation of this modification. This modification involves no unreviewed safety question.
CN-50185
==
Description:==
This modification prcvided for the installation of a Tee and two isolation valves on the 2 inch Main Turbine Leakoff and Steam Seal System (TL) line at the unit I vent.
Flooding of the unit vent area due to influx of large amount of water from the TL System has been a problem.
This modifi-cation allows the TL System drain to be routed to the Feed Drain Tank (FDT) sump when the unit is operating. This modification affects FSAR Figure 10.4.3-2.
Safety Evaluation: This modification eliminates the flooding of the unit vent area due to the influx of water from the TL system. The water from the TL system would flood the Annulus Ventilation System (VE) discharge into the unit vent and j
impair the performance of the VE system prior to the installa-j tion of this TL system modification. This modification is required for the proper functioning of the VE System and corrects a previous design deficiency. This modification does not degrade or result in a functional change of a safety related system. This modification does not pose any unre-viewed safety question.
CN-50199
==
Description:==
This modification provides a displacement type level sensor and control room anrunciation for Lo-Lo Makeup Demineralizer Water System (YM) storage tank level. The 1
previous alarm malfunctioned causing false alarms. This modification also provides manual control option for the YM supply pumps and valve 1YM 230 which will bypass the pressure switch overlocks. This modification affects the instrumenta-tion in the FSAR figure 9.7.3-2 of the Makeup Demineralized Water System and is shared by both Units.
Safety Evaluation: This modification is not safety related and does not pose any unreviewed safety question.
CN-50211
- .ption: This modification provided for the removal of 3
9.
al Dynamics High Pressure Spray Glove Box from the
' M W,
18 of 19 Respiratory Room (512).
This equipment was not being used and was required at a different plant location. This mcdification affects FSAR Figure 9.4.3-5.
Safety Evaluation: This modification does not adversely affect any safety or non-safety system. The modification does not involve any unreviewed safety question.
CN-50230
==
Description:==
This modification provided for the installation of a reduced pressure backflow preventer in parallel with the device previously in service. This modification is shared by both Units and facilitates the periodic testing of the back-flow device in the Potable Water System (YF) as required by South Carolina Drinking Water Regulation 61-587 Section (F)(6).
Safety Evaluation: This modification is not safety related and would not affect any safety system, component or struc-ture. The modification involves no unreviewed safety questions.
CN-50289
==
Description:==
This modification provided for the rerouting and/or resizing of the Fire Protection System (RF) supply line to the Auxiliary Feedwater Pump Room Sprinkler System. Also, unnecessary piping was removed. Piping was rerouted to assure adequate system flow and pressure. This modification is shared by both Units and affects FSAR Figure 9.5.1-5.
Safety Evaluation: This modification increases system reli-ability and corrects a design deficiency. The modification j
does not adversely affect any safety or non-safety system, and it does not involve any unreviewed safety question.
l
)
19 of 19 1
\\
l l
Catawba Nuclear Station Nuclear Station Modifications Completed in Response to NUREG-0737, Supplement 1 During 1986 The following Nuclear Station Modifications were completed during 1986 and corrected Human Engineering Deficiencies (HEDs) identified in NUREG-0737 Supplement 1:
I CN10025, CN10049, CN10210, CN10240, CN10243, CN10267, CN10306, CN10498, CN10536, CN10537, CN10538, CN10539, CN10540, CN10541, CN10542, CN10543, CN10544, CN10545, CN10546, CN10547, CN10548, CN10549, CN10550, CN10551, 1
CN10552, CN10553, CN10554, CN10555, CN10556, CN10557, CN10558, CN10559, CN10562, CN10873, CN20241, and CN50074.
==
Description:==
The preceding modifications corrected HEDs identified as part of the Control Review Process. The subject modifications also meet License Condition Nos. 11 and'7 to Operating Licenses NPF-35 and NPF-42, respectively, and fulfill commitments made in Duke Power's response to NUREG-0737, Supplement 1.
Safety Evaluation:
The subject modifications were the result of Control Review-Activities. These modifications do not adversely impact any system and do not involve any unreviewed safety question.
i 1
1 l
i l
l l
I
1 of 12 CATAWBA NUCLEAR STATION Summary of Procedure Changes, Tests, and
)
Experiments Completed Under 10CFR50.59 for 1986 OP/0/B/6500/39 Radwaste Chemistry Operating Procedure for the Liquid Waste Recycle (WL) System Recycle Monitor Tank (RMT) A Subsystem:
The procedure revision changes the method of how the Recycle Monitor Tank A is used in the procedure. The change will allow processing of Unit I and Unit 2 VUCDT to RMT A and processing RMT A through the Condensate Demineralizer. The affected sections of the FSAR are 11.2.2.1.3, 11.2.2.1.7, 11.2.2.2.1.10, 11.2.2.2.3.4, 11.2.2.2.8.1, and 11.2.2.7.1.7.
This change does not involve any unreviewed safety question.
OP/0/B/6500/40 Radwaste Chemistry Operation Procedure for the Liquid Warte Recycle (WL) System Recycle Monitor Tank (RMT) B Subsystem:
The procedure revision changes the method of how the Recycle Monitor Tank B is used in the procedure. The change will allow the processing of Unit I and Unit 2 VUCDT to RMT B and processing RMT B through the WL Condensate Demineralizer. The affected sections of the FSAR are:
11.2.2.1.3, 11.2.2.1.7, 11.2.2.2.1.10, 11.2.2.2.3.4, 11.2.2.2.8.1, and 11.2.2.7.1.7.
This change does not involve any unreviewed safety question.
TT/1/A/9100/19 RN Train A Flow Balance: Due to a reanalysis by Westinghouse in which various input assumptions were made the CNS FSAR Section 6.2.1.1.3.1 must be changed to meet the criteria.
The probability of an accident or equipment malfunction will not be increased.
This change does not involve any unreviewed safety question.
i TT/0/A/9100/03 Blackout /LOCA RN Flow Check: Acceptance criteria for the Blackout /LOCA RN Flow Check does not match with the required flow listed in the FSAR Table 9.2.1-2.
Westinghouse recom-mended a lower flow rate following their analysis based on heat transfer capacity testing of KC and NS heat exchangers and current ice weights.
This change does not involve any unreviewed safety question.
TP/2/A/2100/02 Controlling Procedure for Zero Power Physics Testing: Accep-tance Criteria "C" in FSAR Table 14.2.12-2 should be changed to read:
"The All-Rods-Out Moderator Temperature Coefficient is negative or rod withdrawal limits have been established in accordance with Technical Specifications". This change to the FSAR allows Westinghouse Criterion for ARO ITC (-1.62 i 3.00 pcm/*F) to be used in this procedure. This change does not involve any-unreviewed safety question.
OP/0/A/6400/06C Nuclear Service Water. This procedure revision requires changes tu FSAR Section 9.2.1.2.3 and Tables 9.2.1-4 and 14.2.12 1 to clarify system alignment for two operating units.
This change does not involve any unreviewed safety question.
l 2 of 12 l
PT/2/A/4250/06 CA Pump Head and Valve Verification: FSAR Figure 10.3.2-2 l
Note 15 to the Flow Diagram of Main Steam to Auxiliary Equip-ment - Main Steam Bypass to Condenser requires change which was submitted to the Catawba Nuclear Station Compliance Section
)
prior to the 4/18/87 procedure change approval date. -Note 15 states, "All SA piping from Main Steam lines in Doghouse to Auxiliary Feedwater Pump Turbine will be electrically heat traced with redundant heat tracing systems to maintain steady state pipe wall temperature of at least 550 F."
(Rev 14 dated 1/31/86) The temperatures for the heat tracings were lowered after studies determined that the higher temperatures were no-longer needed. This change does not involve any unreviewed 4
safety question.
)
OP/0/B/6450/07B Hydrogen - Oxygen Generator Operation: A temporary vent valve 1GS-TV-1 was added to the GS System to purge gases from the YM-make-up line and conserve nitrogen pressurization gas. The change to the FSAR involves the addition of 1GS-TV-1 to the system flow diagram CN-1603-1.0.
The temporary vent valve is located downstream of 1GS-107 at K-14 on the GS System flow diagram. This change does not involve any unreviewed safety question.
PT/0/A/4550/03D Excore Fission Chamber Inventory: This test is not required by the FSAR because it physically inventories special nuclear material. This test does not involve any unreviewed safety question.
OP/1/A/6200/01 Chemical and Volume Control: The Reactor Coolant Filters will be used as post filters for the demineralizers so the inlet valves for the Reactor Coolant Filters will be deleted from both the flow diagram 1154-110 series and the FSAR. This change does not involve any unreviewed safety question.
TT/1/A/9100/32 Reactor Makeup Water Storage Tank Recirculation Time Test:
This test is not described in the FSAR Section 9.3.5 however, Section 9.3.5.2.2.4 " Reactor Makeup Water Cleanup" refers to maintaining Reactor Makeup Water within specifications. This test does not involve any unreviewed safety question.
TT/1/A/9100/35 Refueling Water Storage Tank Recirculation Time Test: This I
test is not described in the FSAR in Section-9.2.7 " Refueling Water System". The procedure provides guidance in determining-the optimum recirculation time required to obtain a represen-tative sample to_ determine if the refueling water quality is within chemistry specifications. This test does not involve any unreviewed safety question.
OP/1/A/6100/09A Annunciator Response for D/G 1A: This procedure change will lower the interlock'setpoint below the Technical Specification (T.S.) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change.
To ensure -
compliance with the current T-S. requirements, the Operations group will verify the absence of the " Tech Spec Warning"
3 of 12 Annunciator for that D/G's tank prior to entering recircula-tion mode for the respective tank. This change does not involve any unreviewed safety question.
OP/2/A/6100/09A Annunciator Response for D/G 2A: This procedure change will lower the interlock setpoint below the Technical Specification (T.S.) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change. To ensure compliance with the current T.S. requirements, the Operations group will verify the absence of the " Tech Spec Warning" Annunciator for that D/G's tank prior to entering recircula-tion mode for the respective tank. This change does not involve any unreviused safety question.
OP/1/A/6100/09B Annunciator Response for D/G 1B: This procedure change will lower the interlock setpoint below the Technical Specification (T.S.) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change. To ensure compliance with the current T.S. requirements, the Operations group will verify the absence of the " Tech Spec Warning" Annunciator for that D/G's tank prior to entering recircula-tion mode for the respective tank. This change does not involve any unreviewed safety question.
OP/2/A/6100/09B Annunciator Response for D/G 2B: This. procedure change will lower the interlock setpoint below the Technical Specification (T.S) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change. To ensure compliance with the current T.S. requirements, the Operations group will verify the absence of the " Tech Spec Warning" Annunciator for that D/G's tank prior to entering recircula-tion mode for the respective tank. This change does not involve any unreviewed safety question.
OP/1/A/6550/01 Diesel Generator Fuel Oil System Operation: This procedure change will lower the interlock setpoint below the Technical Specification (T.S.) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change. To ensure compliance with the current T.S. requirements, the Operations group will verify the absence of the " Tech Spec Warning" Annunciator for that D/G's tank prior to entering recirculation mode for the respective tank. This change does not involve any unreviewed safety question.
OP/2/A/6550/01 Diesel Generator Fuel Oil System Operation: This procedure change will lower the interlock setpoint below the Technical Specification (T.S) limit which corresponds to a minimum tank level that will be determined in a proposed T.S. change. To ensure compliance with the current T.S. requirements, the Operations group will verify the absence of the " Tech Spec Warning" Annunciator for the D/G's tank prior to entering recirculation mode for the respective tank. This change does not involve any unreviewed safety question.
4 of 12 i
OP/2B/6100/10F Annunciator Response for Panel 2AD-S: FSAR Section 10.4.7.5.1
" Alarms and Trips" for the Condensate and Feedwater Systems does not currently reflect system operation. This procedure change was initiated because the CFPT does not trip on receipt of a feedwater isolation signal and to provide additional guidance in resetting the recirculation valves 2CF-6 and 2CF-13.
This change does not involve any unreviewed safety question.
OP/0/B/8400/24 Chemistry Procedure for the Addition of Hydrogen Peroxide to the Reactor Coolant System: Adding hydrogen peroxide to the Reactor Coolant System is not described in the FSAR Section 5.2.3.2.1.
This description was inserted into Section 5 '.3.2.1 and the procedure was created. This change does not involve any unreviewed safety question.
TT/0/A/9100/37A Waste Monitor Tank "A" Recirculation Time Test:
Section 11.2.2.1.4 of the FSAR describes the operation of the Laundry Hot Shower (LHST) Subsystem of the Liquid Waste System and the role Waste Monitor Tank "A" plays in processing and discharging waste for discharge through the Low Pressure Service Water System.
FSAR Section 11.2.2.2.3.9 describes the two (2) Waste Monitor Tanks, however, the recirculation time needed to ensure a representative sample is not mentioned.
The FSAR does refer to samplinF and reprocessing the tanks' contents as needed prior to die :5arge from the plant. This test does not involve any unreviewed safety question.
TT/0/A/9100/37B Waste Monitor Tank "B" Recirculation Time Test:
Section 11.2.2.1.5 of the FSAR describes the operation of the Floor Drain Tank (FDT) Subsystem of the Liquid Waste System and the flow path of liquids from the FDT to Waste Monitor Tank "B" for release. This section also describes how the effluent may be sent to the Laundry Hot Shower Tank Subsystem for processing if needed prior to discharge.
FSAR Section 11.2.2.2.3.9 describes the two (2) Waste Monitor Tanks, however, the recirculation time needed to ensure a representative sample is not mentioned. The FSAR does refer to sampling and reprocessing the tanks' contents as needed prior to discharge from the plant.
This test does not involve any unreviewed safety question.
TT/1/A/9100/36 Boric Acid Tank Recirculation Time Iest:
Section 9.3.4.2.3.8 5
of the FSAR refers to sampling the Boric Acid Tank, but the Boric Acid Tank Recirculation Time Test to ensure a repre-sentative sample of the tank's contents is not included.
This test does not invc1ve any unreviewed safety question.
OP/1/B/6300/09 Turbine Lube Oil Transfer Purification:
Section 10.2.2 of the FSAR provides an overview of the Main Turbine Lube Oil and Purification (LT) System but does not describe filling and draining the LT and the Generator Seal Oil (LG) Systems addressed in the procedure revision. This change does not involve any unreviewed safety question.
5 of 12 OP/2/B/6300/09 Turbine Lube Oil Transfer and Purification:
Section 10.2.2 of the FSAR provides an overview of the Main Turbine Lube Oil and Purification (LT) System but does not describe filling and draining the LT and the Generator Seal Oil (LG) Systems.
addressed in the procedure revision. This change does not involve any unreviewed safety question.
OP/0/A/6400/06C Nuclear Service Water System: Enclosure 4.15 was added to the procedure which allows a lube injection strainer to be out of service for only 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as outlined in the procedure enclosure is more conservative than the requirements listed in the FSAR Table 9.2.1-4 Item 21.
This change does not involve any unreviewed safety question.
TP/2/B/2600/15 Process and Effluent Radiation Monitor Test: This procedure change transfers the FSAR Start-up test requirements for the Waste Gas Effluent discharge monitor (EMF-50) to TP/0/B/2600/15A
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(EMF 50 Waste Gas Monitor Correlation Test) which is currently under development and is scheduled for approval when the modifications for the Waste Gas System are completed. The affected sections of the FSAR are Table 14.2.12-2 (Page 22)
I and Figure 14.2.11-1.
This change does not involve any unreviewed safety question.
TT/0/A/9100/38 Diesel Fuel Oil Storage Tank Recirculation Time Test:
Section 9.5.4.2.1 of the FSAR describes the general operation of the Diesel Generator Fuel Oil System but, does not include the Diesel Fuel Oil Storage Tank Recirculation Time Test that determines the amount of recirculation time needed to ensure a representative sampling of the tank's contents. This test does not involve any unreviewed safety. question.
PT/0/A/4400/08 RN Flow Balance for Degraded Mode: Table 9.2.1-2 " Nuclear Service Water System Flow Rates" Items number 1, 5, 8 and 9 of the FSAR require change to comply with the new design flow rates recommended in the Nuclear Service Water (RN) Test Acceptance Criteria Data Sheet Revision 2 dated 9/23/86.
This change does not involve any unreviewed safety question.
OP/1/A/6100/09B Annunciator Response for D/G IB Panel:
FSAR Section 9.5.4.2.1 discusses the recirculation pump interlock that ensures that the pump will not drain a Diesel Generator Engine Fuel Oil System tank below the Technical Specification limit should a pipe break occur. This modification lowers the interlock setpoint. A lower setpoint is appropriate because the intent of the interlock can be met. by utilizing modified surveillance methods. The modification does not represent an unreviewed safety question.
OP/2/A/6100/09B Annunciator Response for D/G2B Panel:
FSAR section 9.5.4.2.1 discusses the recirculation pump interlock that ensures that the pump will not drain a Diesel Generator Engine. Fuel Oil System tank below the Technical Specification limit should a pipe break occur. This modification lowers the interlock
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setpoint because the intent of the interlock can be met at the i
lower setpoint by utilizing modified surveillance methods.
The modification does not represent any unreviewed safety question.
P/2/A/6350/05 Alternate A/C Power Sources Procedure: This revision i
concerns the alternate AC power sources described in the FSAR j
Sections 8.3.1.1.1 and 8.3.1.1.2.
This revision reflects the
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minor changes of equipment wiring in the procedure. The changes of the wiring were made to prevent unexpected loss of electrical equipment due to loss of an MCC (Motor Control Center). This revision of the procedure is minor and does not pose any unreviewed safety question.
'PT/2/A/4550/03C Core Verification Procedure: This revision of the procedure removes the requirement to visually check the I.D. of the Rod Control Cluster Assembly (RCCA) in proper location as previous-ly required by FSAR Section 14.2.10.1.
Since all RCCAs are very similar it is only required to verify that core locations which are to have RCCAs actually have them.
Verification of the RCCA's I.D. number in situ does not serve any purpose and is extremely time consuming and cumbersome.
In the unlikely event.that RCCA's are shuffled among fuel assemblies there is still no safety significance of mislocating the RCCA's.
In initial fuel loading all RCCA's have no fluence and correcting g.
the fuel loading pattern is not a serious problem. This revision of the procedure (FSAR Section 14.2.10.1) does not 3
pose any unreviewed safety question. The FSAR accident analyses do not consider any particular pattern for the initial placement of the RCCA's and a misplacement of RCCA's does not have any safety implication.
TT/1/A/9100/19 Nuclear Service Water Train A Flow Balance: This test has been performed pursuant to a new analysis by the Westinghouse using the most recent numbers for the containment ice weight, active sump volume and heat transfer capacities. The new analysis allows the nuclear service water requirements for the containment spray heat exchanger to be reduced to 4500 gpm and the nuclear service water requirements for the Component Cooling heat exchanger to be reduced to 7000 gpm. This test does not pose any unreviewed safety question.
TT/0/A/9100/03 Blackout /Loca Nuclear Service Water Flow Check: This test is conducted pursuant to a new analysis by Westinghouse based on testing of the heat transfer capacities of the Component Cooling (KC) water heat exchanger, the Containment Spray (NS) heat exchanger and the current ice weight in the containment.
This analysis reduces the analyzed acceptable flow rate from the nuclear service water to the KC and NS heat exchangers to greater than 7000 gpm and 4500 gpm respectively. The performance of this test does not create any adverse safety implications since the nuclear service' water would be either in the
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" accident alignment" or capable of being placed in this mode within one minute. This test does not pose any unreviewed 1
safety question.
PT/1/A/4150/14B Water Flow Rate Determination Using Radioactive Tracer:
This procedure provides a means of determining water flow rates in the condensate system using trace quantities of radioactive Na-24 isotope. Use of radioactive tracers does not have any safety related implications. This new procedure does not pose any unreviewed safety questions.
OP/1/A/6450/10 Unit 1 Containment Hydrogen Control System Procedure: This revision of the procedure allows manual operation of the containment air return fans when the cooling of the containment is desired and the lower containment chillers are inoperable.
The procedure is concerned with the Containment Hydrogen Control System and the revision requires that FSAR Figure i
9.4.10-1 show valves VX-3 to VX-28 as throttled. This revis-ion of the procedure does not pose any unreviewed safety question.
OP/2/A/6450/10 Unit 2 Containment Hydrogen Control System Procedure: This revision of the procedure allows manual operation of the containment air return fans when the cooling of the containment j
is desired and the lower containment chillers are inoperable.
The procedure is concerned with the' Containment Hydrogen Control System and the revision requires that FSAR Figure 9.4.10-1 shows valves VX-3 to VX-28 as throttled.
This revis-
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ion of the procedure does not pose any unreviewed safety question.
OP/2/A/6100/09A Annunicator Response for D/G 2A Panel: This revision of the j
procedure incorporates the change of the trip setpoints for i
the fuel oil tank recirculation pump.
The fuel oil tank recirculation would be tripped or pump blocked from starting at or below 77% of the ' full' tank level. The diesel generator annunciator panel would display this and the related information.
The revision of the procedure concerns the display information in the the diesel generator annunciator only, no other changes are being made by the revision of the procedure. This revision of the procedure does not pose any unreviewed safety questions.
OP/1/A/6100/09A Annunicator Response for D/G 1A Panel: This revision of the procedure incorporates the change of the trip setpoints for the fuel oil tank recirculation pump. The fuel oil tank recirculation would be tripped or pump blocked from starting at or below 77% of the ' full' tank level. The diesel generator annunicator panel would display this and the related information. The revision of the procedure concerns the display information in the diesel generator annunciator only, no other changes are being made by this revision of the procedure. This revision of the procedure does not pose any unreviewed safety questions.
8 of 12 OP/1/A/6550/01 Unit 1 D/G Fuel Oil System Operation Procedure:
This revision of the procedure is implemented pursuant to a proposed Technical Specification amendment removing an interlock (FSAR Section 9.5.4.2.1, Pg. 9.5-10) on the diesel generator fuel oil recirculation pump and replacing it with a surveillance requirement. The purpose of the interlock is to ensure that the fuel supply in the fuel tank would not be pumped down below the Technical Specification limit should a pipe break occur. The proposed modification of the Technical Specification lowers the fuel tank level setpoint to below the present Technical Specification value.
The new setpoint being used corresponds to a minimum tank level based on a new analysis. To ensure compliance with the present Technical Specifications the operations group will verify that
" sufficient fuel capacity" exists for the affected diesel generator every half hour while the unit fuel recirculation pump is in operation.
This surveillance is not performed when the associate diesel generator is inoperable. This procedure assures that no Technical Specifications will be violated during the period the proposed Technical Specifications are being approved. This revision of the procedure does not pose any unreviewed safety questions.
OP/2/A/6550/01 Unit 2 D/G Fuel Oil System Operation Procedure: This revision of the procedure is implemented pursuant to a proposed Technical Specification amendment removing an interlock (FSAR Section 9.5.4.2.1, Pg. 9.5-10) on the diesel generater fuel oil recirculation pump and replacing it with a surveillance requirement. The purpose of the interlock is to ensure that the fuel supply in the fuel tank would not be pumped down be]cw the Technical Specification limit should a pipe break occur. The proposed modification of Technical Specifications lowers the fuel tank level setpoint to below the present Technical Specification value. The new setpoint being used corresponds to a minimum tank level based on a new analysis.
To ensure compliance with the present Technical Specifications the operations group will verify the
" sufficient fuel capacity" exists for the affected diesel generator every half hour while the unit fuel recirculation pump is in operation. This surveillance is not performed j
when the associated diesel generator is inoperable. This procedure assures that no Technical Specifications will be violated during the period the proposed Technical Specifications are being approved. This revision of the procedure does not pose any unreviewed safety questions.
OP/1/A/6200/10 Upper Head Injection Procedure - Unit 1: This modification to the procedure reduced operator time to start the UHI makeup j
and testing pump. Also, the suction and miniflow valves were changed from closed to open in order to provide an assured recirculation flow path for the pump at the time the pump break is closed. This procedure affects FSAR Figure 6.3.2-5, and does not involve any unreviewed safety question.
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OP/1/B/6300/01 Turbine Generator Procedure: This procedure revision concerns the Turbine Generator System. This procedure is rewritten to make certain operating instructions more specific and also utilize more specific nomenclature. This revision only provides greater clarity in instructions and does not omit or
' introduce new information.
This revision of the procedure does not pose any unreviewed safety question.
OP/0/B/6500/33 Radwaste Chemistry Operating Procedure For Liquid Waste Recycle (WL System), Floor Drain Tank Subsystem: This j
revision of the procedure reflects the addition of Floor Drain Tank (FDT) filters A and B to replace the FDT filter per station modification NSM-50151.
This procedure or the equip-ment involved is not safety related and revision of the-procedure to reflect as built conditions does not pose any unreviewed safety question.
OP/0/B/6500/40 Radwaste Chemistry Operating Procedure For liquid Waste Recycle (WL System), Recycle Monitor Tank B Subsystem: This revision of the procedure was made to reflect the current j
practice of using the Recycle Monitor Tank (RMT) "B" for processing the Unit I and Unit 2 Ventilation Unit Condensate Drain Tank (VUCDT) contents. The VUCDT contents are trans-ferred to RMT "B" monitored for radioactivity and then pro-cessed through the liquid radwaste (WL) system condensate demineralizers if appropriate. This revision affects YSAR Sections 11.2.2.1.3, 11.2.2.1.7, 11.2.2.2.1.10, 11.2.2.2.3.4, 11.2.2.2.8.1 and 11.2.2.7.1.7.
This revision is not safety related.
This revision of the procedure does not pose any unreviewed safety question.
j OP/0/B/6500/39 Radwaste Chemistry Operating Procedure For Liquid Waste i
Recycle (WL System), Recycle Manitor Tank A Subsystem: This revision of the procedure has been made to reflect the current practice of using the Recycle Monitor Tank (RMT)
"A" for pro-cessing of the Unit I and Unit 2 Ventilation Unit Condensate Drain Tank (VUCDT). The VUCDT contents are usually non-contaminated water these evitents are transferred to the RMT j
"A" for monitoring for radtoactivity and processed through a condensate demineralizer if not radioactive. This procedure assures cost savings on processing of non-radioactive wastes.
This procedure affects FSAR Sections 11.2.2.1.3, 11.2.2.1.7, 11.2.2.2.1.10, 11.2.2.2.3.4, 11.2.2.2.8.1 and 11.2.2.7.1.7 and is not safety related. This revision of the procedure does not pose any unreviewed safety question.
OP/2/A/6200/10 Unit 2 Upper Head Injection Procedure: There are two change:
to this procedure.
The first change takes into account the installation of the relief valve 2NV-989 to the suction piping of the PD (positive displacement) pump. This eliminates the possibility of overpressurization of the PD pump suction piping when the mini-flow valve (2NV-477) is open. The second change to this procedure is that the mini-flow valves (2NI-356, 2NI-357 and 2NI-Da) are changed from normally closed to normally
i 10 of 12 open to reduce operator time in starting the Upper Head Injection (UHI) makeup and testing pump. This procedure revis-ion affects FSAR Figure 6.3.2-5 where the valves 1NI-356, 1NI-357 and 1NI-358 are now shown as normally open.
PT/0/B/4600/13 Test Procedure for Determining the Accuracy of Eppendorf Pipets: This Periodic Test (PT) concerns the measurement of the accuracy of each Eppendorf pipet. The chemistry personnel have routinely tested all pipets used in the chemistry section i
at the plant. This periodic testing procedure is being generated to reenforce and formalize this practice to ensure reliable chemistry analysis in the laboratory. This procedure complies with the practices. recommended by INPO.
This procedure is not safety related and incorporation of this procedure in station operating procedures does not pose any unreviewed safety questions.
OP/0/A/6200/22 Operating Procedure for Cleaning the NS Heat Exchanger:
This procedure provides for the installation of temporary piping required to clean a Containment Spray System (NS) Heat Exchanger. This procedure affects only the Nuclear Service Water System (RN) side of the exchanger. Even if the temporary piping leaks, there would be an adequate supply of RN.
This procedure affects FSAR Section 6.2.2, Table 6.2.2-2, and Figure 9.2.1-9.
The margin of safety as defined I
in the FSAR is not reduced, and no unreviewed question is involved.
PT/2/A/4350/12 Diesel Generator And Voltage Regulator Test. This revision of the procedure deletes the requirement to test start the diesel generator engine (2A and 2B) under mechanical governor control only.
When the diesel generator engine is started under mechanical governor control only, some overshoot of the 3
governor setpoint occurs.
In general this overshoot exceeds the limit of 484 RPM set in the TDI (Transamerica Delaval, Inc.) Diesel Generator Owner's Group Design Review and Quality Revalidation Repor* (DRQR).
In addition to exceeding limits in this situation t 2 cugine speed will approach a crankshaft critical speed of 4.6 RPM.
While time of engine operation near critical speed is short operating in this range should be avoided as far as possible. This test requirement j
is being deleted because it serves to verify proper operation of the mechanical governor a feature also verified by other sections of the periodic testing procedure thus making this test requirement unnecessary and potentially damaging to the diesel generator engines.
This revision of the procedure does not pose any unreviewed safety question.
OP/0/A/6200/02 Operating Procedure fc; Cleaning the KC Heat Exchanger: This procedure provides for the installation of a smal.' recirculation pump in order to clean a Component Cooling System (KC) Heat Exchanger. The Nuclear Service Water System is rafficiently oversized to more than compensate for any leak that may occur through the small recirculation pump. This procedure affects 1
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FSAR Sections 9.2.1 and 9.22, Table 9.2.1-2, and Figuo.s 9.2.1-6 and 9.2.1-10.
This procedure does not affect the margin of safety
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as defined in the FSAR, and it does not involve any unt w iewed i
safety question.
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1 TP/2/A/2100/01 Controlling Procedure for Power Escalation:
This procedure deletes the requirement to perform " Doppler Only Power Coefficient" test at i
50% and 90% power level for Unit 2.
The performance of the Doppler l
only power coefficient test does not verify any functional capability of safety related equipment. Deletion of this test
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requirement does not have any safety implication. Adequate margin j
exists between the values of the Doppler only power coefficients i
used in the FSAR accident analyses and the measured values. Actual testing on Unit I has demonstrated that the conservative values
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used in the FSAk analysis are never approached. Therefore, it is not necessary to conduct the " Doppler Only Power Coefficient" tests and measurements on Unit 2 since both units are very nearly 4
identical and results of Unit 2 for Doppler Only Power Coefficient are not significantly different from that for Unit 1.
This revision of the procedure is not safety related. This revision affects FSAR Table 14.2.12-2 and also changes some wording on FSAR
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Figure 14.2.11-1.
This revision of the procedure does not pose any unreviewed safety question.
PT/2/A/4150/19 I/M Approach To Criticality Procedure:
This procedure provides for a safe controlled approach to criticality.
In the test me.thod section of the FSAR it was previously stated that Boron dilution of the reactor coolant would continue till the ICRR value reaches 0.05.
The actual procedure uses a more conservative value of ICRR of 0.2 as the approximate point for stopping dilution. This is conservative compared to the previous FSAR value. Therefore, the FSAR is being changed to reflect a more conservative test procedure value.
This revision of the test procedure as described in the FSAR does not pose any unreviewed safety question, l
TP/2/A/1400/01 Nuclear Service Water System Functional Test Procedure:
This Unit 2 procedure was revised to indicate that it was not necessary to perform a flow balance for "small LOCA" and " Refueling" modes of system operation. These two modes do not balance any equipment that was not covered by previous flow balances. Also, performance of these two balances would have caused operability prcblems for Unit 1.
FSAR Table 14.2.12-1 was previously updated to reflect this change.
This change does not pose any unreviewed safety question.
Temporary Operating Procedure for Cleaning the IB Containment Spray Heat Exchanger 1
(NS): This procedure provides for the installation of temporary piping required to clean the IB Containment Spray Heat Exchanger. This procedure affects only the Nuclear Service Water (RN) System side of the exchanger.
Even if the temporary piping leaks, there would be an adequate supply of RN.
This procedure affects FSAR Section 6.2.2, Table 6.2.2-2, and Figure 9.2.1-9.
The margin of safety as defined in the FSAR is not reduced, and no unreviewed safety question is involved.
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12 of 12 Unit 1 UHI Thermal Sleeve Nozzle Safety Evaluation: A UHI thermal sleeve (UHI T/S) nozzle was discovered to have become loose and detached from its thermal sleeve and had fallen onto the upper ledge of the upper internals. No apparent damage was caused by the action of the loose nozzle inside the upper head region. A safety analysis was conducted on October 22, 1986 to evaluate the consequences of other 3 thermal sleeve nozzles becoming detached during plant operation.
Westinghouse evaluated the impact loading on the UHI T/S nozzle as well as the consequences of the detached UHI T/S nozzle on the components in the upper head region. All the stresses and loadings due to the loose UHI T/S nozzle are found to be within the ASME Section III Code limits. Based on this detailed safety evaluation the i
detachment of the remaining 3 UHI T/S nozzles at Catawba Unit 1 during plant operation for the current cycle does not constitute an unresolved safety question as defined by 10 CFR 50.59.
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