ML18005A718
| ML18005A718 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/28/1988 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| HO-880226-(O), NUDOCS 8812050254 | |
| Download: ML18005A718 (27) | |
Text
A.C CE1ZRATED DIST'RIBUTlON DKMONSTRA,TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8812050254 DOC.DATE: 88/11/28 NOTARIZED NO DOCKET N FACIL:50-400 Shearon Harris Nuclear Power Plant; Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION WATSON,R.A. Carolina Power 8 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards quarterly rept of changes to procedures plant
& t mods described in FSAR for Third Quarter 1988.
ENCL 'IZE:
orQExperim nts Made IE47D COPIES RECEIVED:L'TR
'5000400 CODE: D I'ISTRIBUTION TITLE:, 50.59 Annual Report of Changes, Tests e ~
W/out Approv S
NOTES:Application for permit renewal filed.
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTD ENCL ID CODE/NAME ENCL
'VTR PD2-1 LA 1 0 PD2-1 PD 5 5 BUCKLEY,B 1 0 INTERNAL: ACRS 6 6 AEOD/DOA 1 1 AEOD/DSPy'TPAB 1
'1 1 NRR/DLPQ/HFB 10, 1 1 NRR/DOEA/EAB 11 1 ~RPB 10
'. 2 2 NUDOCS-ABSTRACT 1 1 FILE 02 1 1 RGN2 FILE 01. 1 1 ~ ~
EXTERNAL: LPDR 1 NRC PDR 1 1 NSIC 1 R
D.
h D
NOZE TO ALL RIDS" RZCIPIEÃIS D
8 PIZASE HELP US IO RECCE %ANDRE! CXÃI'ACT 'THE DOCUMENT CDNXBOL DESKS ROOM Pl-37 (EXT. 20079) K) XZZHXNA!ZE YOUR NAME PRES DISZRIBVXXON LISTS POR DOCUMENZS YOU DQNiT NEEDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23
ZcM~~- 't'A'4l Carolina Power 8 Light Company pgV 28 1966'ARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 File Number.'SHF/10-13510C 10CFR50.59 Letter Number'HO-880226 (0)
'.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARBIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 UARTERLY REPORT IN ACCORDANCE WITH 10CFR50.59 Gentlemen'.
0 In accordance with 10CFR50.59 and CPSL Letter (NLS-86-454) of commitment dated December 9, 1986, the following report for the third quarter of 1988. This report contains is'ubmitted
.brief . summaries of changes to procedures and/or plant modifications, which change the plant as it is described in the FSAR. There were no tests or experiments conducted during this interval, which are not described in the FSAR which require reporting in this report.
Very truly yours, R. A. Watson Vice President Harris Nuclear Project MGW:crc Enclosure ~
cc'Mr. W. H. Bradford (NRC SHNPP)
Mr. M. L. Ernst (NRC - RII) 8812060254 881128 ADOCK 05000400 PDR PDC Agw7
%EM/HO-8802260/Page 1/OSl
CHANGE TO PROCEDURE AS DESCRIBED IN THE FSAR Title'CRC-001, Rev. 4, SHNPP Environmental and Chemistry Sampling and Analysis Program Functional'ummar 'Procedure CRC-001 specifies the Harris Plant chemistry sampling and analysis schedule. It addresses routine sample points and provides limits where appropriate. CRC=001 previously included benzene insoluble test methods for. Emergency Diesel Generator Lube Oil. Testing for benzene insolubles has . keen replaced.'ith testing for toluene insolubles.
Benzene insolubles was 'a test which when'sed in conjunction with pentane insolubles, would provide the amount'f oxidized material, soaps, and asphaltic material present in used oils. Because. of the carcinogenic nature II of benzene, the benzene iniolubles test will no longer be run, Safet Summar '. Tolu'ene insolubles is
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an acceptable substitute for benzene insolubles. -ASTM D893-85., Standard Test Methods for Insolubles in Used Lubricating Oi,l, tests oil using pentane and toluene insoluble test methods.
The standard no longer has a test method employing benzene. Changing to is technically correct and allows testing of oil per current standard 'oluene test methods.
This change does not increase the probability or consequences'f analyzed accidents, nor introduce a different type of accident oi.equipment malfunction than already evaluated in the FSAR. Thus; no unreviewed .safety question exists.
FSAR Reference. Section 9.5.7.4 MEM/HO-8802260/Page 1/OS1
CHANGE TO PROCEDURE AS DESCRIBED IN THE FSAR
Title:
CRC-812 Revision 2, Dew Point Functional Summar .'Procedure CRC-812 provides the method of measuring the dew, point of air in systems such as the Instrument Air, Emergency Diesel Generator (EDG) Starting Air, and Breathing Air Systems. CRC-812 Revision 2 changes the EDG Starting Air dew point monitoring location from the air dryer effluent to the air receiver effluent .and provides a .-20'F dew point as an operating limit.
Safet Summar 'The
. EDG initial and possible subsequent EDG starts are performed on stored. air normally without operation of the air compressor/air dryer. Monitoring of stored air dew point provides better assurance of'DG operability. Maintaining the, st'ored air in the air,receiver at a,-20'F or less dew point will prevent fo'rmation of ice in .the EDG'tarting Air Distributers that distribute pilot air to open the Air Starting valves in sequence on each of the diesels cyli'nder. 4
, This chaqge does not increase the probability or consequences of analyzed accidents, nor introduce a different type of .accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
FSAR Reference'. Section 9.5.'6 MEM/HO-8802260/Page 2/OSl
Title:
DRPI exists.
FSAR PCR-000031, Functional
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120'F.
Summar '.
1A and 1B DRPI cabinets.
CHANGE TO Digital Reference. 'Figure 6.2.2-3 Rod
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FACILITY AS DESCRIBED IN THE FSAR Position Indication (DRPI) Cooling This plant modification installed HVAC duct work to the The ductwork provides approximately 250 ACFM to each cabinet for cooling in an effort to maintain the. cabinet temperature belo~
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Du'ctwork to the c'abinets was routed from existing ductwork at elevation 286'f the Reactor Containment Building.
'ere, applied to, the modification. As a result,,the HVAC support for the modification has been seismically designed to prevent any interaction with system. ~
This change does not increase the probability or consequences of analyzed cabinets are located inside containment and the recommendation of RG 1.29 accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question a'.safety MEM/H0-8802260/Page 3/OS1
CHANCE TO FACILITY AS DESCRIBED IN THE FSAR Title'. PCR-000064, Emergency Service Water (ESW) Screen Wash Pump Flow Meter Functional Summar .'This modification provides flow elements on the suction lines of the emergency service water screen wash pumps to determine the pump flow rate. The flow rate and discharge pump pressure will .be used to evaluate pump degradation during periodic in-service- testing. The emergency service water screen. wash pumps- provide seyl, water,to ESW pumps-and screen .wash water to the traveling screens. This modification adds orifice flanges and an orifice plate (1/8" thick) with 2.651" concentric bore to the suction line of each screen wash pump. Instrument valves are used'n flange pressure taps to
.". ensure minimal impact to pipe stress and hanger loads.
Safet carbon Summar stainless
'All of steel 0
the installed 'components will be ASME III,'lass qualified materi.'al to ensure'eismic/structural 3,
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integrj.ty. The design meets the same .criteria as the original installation.
~ ~ Since the instrument lines associated with this modification will be used only during ISI testing, they will be capped to provide additional isolation.
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident'r equipment" malfunction than already evaluated, in the FSAR. Thus,'o unreviewed safety question exists ~
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References:
Figure 9'.2.1-1 MEM/H0-8802260/Page 4/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR 000264, Turbine Lube Oil Reservoir Vapor Extractor Functional Summar . This modification provides a redundant vapor extractor on the Turbine Lube Oil Reservoir to improve the unit availability. The design mounts a second vapor extractor (pump and motor) or the Turbine Lube Oil Reservoir. It and the existing vapor--extractor "draw suction from a common outlet on the Turbine Lube Oil .Reservoir .and discharge into .a common header..
Each is provided with "blast-gate" valves to regulate flow and check valves on the outlets to prevent backflow.- The vapor extractor housing drains are piped together into a common drain. One pressure tap with an isolation valve is provided. for instrumentation and contro'1.,'ystem',
therefore, possibility for failure of the system is reduced.', The redundant vapor extractor reduces the possibil'ity for oil leakage qr hydrogen buildup in the lubrication system, therefore, reducing the possibility for fire. The redundant vapor extractor is the same type, size, and material as the original vapor extractor. All mechanical items added are the same type, material, and pressure rating as the original components; therefore, material is maintained. 'ompatibility J
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This change 'does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or, equipment malfunction than already 'valuated in the FSAR; Thus, no unreviewed safety 'question Oxlsts ~
Reference:
Figure 10.2.2-9 MEM/HO-8802260/Page 5/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-000741, Component Cooling Water (CCW) Check Valve Testing Functional Summar 'This modification installed test connections which will allow performance of ASME Section - XI valve testing of check valves 3CC"V276SN-1 and 3CC-V277SN-1 located in CCW line 3CC4-626SN-1 downstream of the processing sampling panel'. . The previous .piping configuration--did not allow ISI testing of= these check, valves.
The CCW line is required to provide a maximum primary sample temperature of 120'F to the sampling panel. ~
The CCW to this nonsafety processing sampling panel is provided with two air operated valves on'he inlet and tpo check valves on the outlet .side. ,The panel is located in a',separate cubj,cle on
.elevation 236', of the RAB which is inaccessible during post-accident.
4 This modification adds 1" lines with two.globe valves and pipe cap around the two existing check valves 3CC-V276SN-. 1 and 3CC-V277SN-1,. These check valves are classified as isolation valves from the primary sampling panel IA-NNS and CCW line 7CC4-409-1. These check valves are considered "the class break 3CC4-626SN-1.
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between a class 3 and a class 7 line. The new test lines will be connected to line carbon steel qualified material to ensure seismic/structural integrity. Since these'ines will be used only during ISI testing, they will be capped to provide additional isolation. No~additional credible failure modes'ill be introduced by adding the 1" drain lines.
4 9 t This change does not increase the probability'r consequences of analyzed accidents, nor introduce a different t'ype of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
Reference:
Figure 9.2.2-01 MEM/H0-8802260/Page 6/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR 001069, NLL Cards for Steam Generator Level Channels Functional Summar : This plant modification supported the installation of a 1.5 second filter to the Steam Generator Low-Low Level Reactor Trip and Steam Generator Low, Coincident with Steam/Feedflow Mismatch Reactor Trip channels in the Shearon Harris -Plant. Previously,,the non-LOCA safety analyses assumed a 2.0 second response -
time for 'eactor .trip for the - Low-Low Level trip function (the Mismatch trip is not assumed in any of the safety analyses). A 1.5 second - increase in responsh time required that ,the safety analysis assumption increase to 3.5 seconds.
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-, functions mentioned above will ~
impact any, of the safetyh analyses which takes .
credit for these trips for protection. Those transients 'include.
- 3. Ff;ed Line Break To address the impact on the above events, each transient was reanalyzed with a 3.5 second readtor trip response time. The results of the reanalysis were within the appl1cable safety criteria discussed in the FSAR. Therefore, the installation ef the time filters (and the resulting 3.5 second total response time assumption) is acceptable with. respect to the conclusions presented in the non-LOCA safety analyses in the Shearon Harris FSAR.
he This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewe'd safety 'question exls'ts ~
FSAR Reference. 'Section 15.0 6 15.2 Section 16.3 MEM/H0-8802260/Page 7/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title. PCR"001841, Fuel Handling Building Sprinkler System Drain Functional Summar 'This plant modification provides drain piping from the Fuel Handling Building sprinkler system-main drains into the condensate drain system to prevent the sprinkler drain water from entering the radwaste drain system. The modification also adds check valves in the drain piping and seals the drains to prevent back flow or splash .back when discharging from the main
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drain at high volume/veloc'ity.
type, and grade, schedule, and ,,'pressure rating, as the original ,system components', therefore, the system fntegrityis maintained.. Sealing, thy drains and hard, piping the main drain into the,,condensate, drain" system,eliminates the, possibility for splashing on electrical equipment. The open drains were previously overflowing from the high velocity flashes. Hard piping inj:o the condensate drain system also eliminates the possibility for flooding.'his change does not increase the probability or consequences of analyzed
.accidents, nor introduce a diffe'rent type of accident or equipment, malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exi'sts. ~ ~
FSAR Reference'Figure 9.3.3-3 ~ ~
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Q MEM/HO-8802260/Page 8/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-002031, Thrust Bearing Instrumentation Functional Summar '. This modification replaces the main turbine rotor position instrumentation which had proven to be unreliable, with new instrumentation provided by Westinghouse. This component is part of the turbine supervisory control system and provides indication of thrust bearing wear. The modification will improve reliability and provide more accurate
,indication of thrust bearing wear to Operations personnel.
1
.'.turbine thrust, bearing wear.
The component is mounted'in a non-safety related system.
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This change does not increase the'robability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated, in the FSAR. ~ Thus, no unreviewed safety question
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exists.
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Reference:
Figures 10.2.2-9 and'0.2.2-10
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HEM/HO-8802260/Page 9/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-002109, Program for Reactor Coolant System (RCS) Unidentified Leak Rate Detection Functional Summar '. This plant modification adds a new function to the plant computer also known as .the ERFIS computer). The purpose of this function is to calculate the conta'inment sump leak .rate by monitoring, the two containment sump level points., ~ .It will calculate""1'eak rates every thirty minutes and alarm the operator via an ALB Main Control Board annunciator if either leak rate exceeds the rate of the previously calculated leak rate by 0.76 gpm or if the leak rate exceeds the last hour's leak rate by 0.76 gpm. s A
~ ~ ~ ~ s This modification was implemented to replace the containment sump. fl'ow element FE-7164,.which was removed by PCR-002318. This element was, designed to measure ~
s
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flow into the containment sump.
a 10CFR50, Appendix A, Criterion 4 and 30 and Regulatory Guide 1.45.
Regulatory Guide 1.45 specifies the following.'
c,.5 The sensitivity and response, time of each'eakage detection system f'r
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employed unidentified leakage 'should be adequate ..to detect .a leakage rate of one gpm in less than one hour.
c.7 .Indicators and alarms ,for each leakage detection system should be provided in the main control room.
The proposed system meets these requirements. By calculating a leak rate every '30 minutes based on the last 30 minutes level changes the program will detect and alarm a .1 gpm increase within one hour. The ALB and computer alarm information is available in the control room.
This system does not add any additional instrumentation.
level instrumentation and computer facilities. 't It uses existing does not control or activate any equipment other than the ALB's on the main control board.
Failure or malfunction of this system could at worst cause a malfunction of other software on the plant computere This computer does not and cannot control safety related equipment or equipment important to safety.
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. In addition, the sump inleakage flow determination by'hanges in sump level have proven to be more accurate than the flow element. Thus, no unreviewed safety question exists.
FSAR Reference. 'Section 5.2.5 MEM/H0-8802260/Page 10/OS1
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CHANGE TO, FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-002307, Installation of Inspection Ports on Feedwater Flow ~
Elements and Flow Straighteners in Feedwater Lines.
Functional Summar . 'This plant modification installed inspection/cleaning ports on each main feedwater flow element and installed flow straighteners in the feedwater lines upstream of each main flow element. The, function of the feedwater system is to deliver feedwater to-=the steam -generators at the required flow rate, for any pl,ant power level.
In the case of the Harris PLant feedwater system, piping configuration and design do not provide for optimum accuracy of the flow, reading from .the main feedwater flow elements. The lack of inspection ports leaves no. means for determining, the amount of fouling on, the flow element surfaces or for, cleaning those surfaces should fouling exist. Since. fouling will adversely affect flow measurement readings, a correction factor must be applied to account for this uncertainty. Similarly,, the lack of either flowstraighteners or sufficient runs of strai;ght pipe upstream of the flow elements necessitates use of a correction factor due to flow turbulence at the element inlets. The elements are calibrated 'based on smo'oth fluid flow', the turbulence at the inlets results in a degree of uncertainty in the instrument readings.
normal system and plant performance. However, these are new components which create" new potential failure modes in the feedwater system which requi'red evaluation. The applicable safety 'considerations are mechanical failure of the inspection ports and straighteners and the possible consequent effects on cbntrol signal failure (main flow elements), containment isolation, and Steam generator integrity. 4 The design of the inspection ports and flow straighteners is commensurate with other similar components in the feedwater and condensate system. Therefore, the probability of a failure which could have adverse impact on feedwater flow capability, feedwater isolation capability, or on the steam generator integrity is not increased.
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus,'o unreviewed safety question exists.
FSAR Reference. 'Figures 10.4.7-2, 10.1.0-3, 3.6A-33.1 MEM/HO-8802260/Page 11/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-002319, Condensate Polishing Demineraliaer System (CPDS) Hot Water Tank Relief Valve Functional Summar . 'This modification revised the set point of the pressure relief valve for the CPDS Hot.Water Tank from 100 PSI to 98 PSI. The purpose of the hot water tank is to raise the temperature, of the dilute caustic to 120 F in order to 'enhance;,the removal of silica from -the;resin. The previous design set the relief valve for,the CPDS hot water tank higher than the tank's maximum allowable working pressure. The tank is built to ASME Section IV,and is rated at 98 PSIG (maximum allowable working pressure). This set point
'hange. is not an enhancement,. but brings the operation of the .hot water tank within, bhe design, specification..
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release path to the environment 'and has no safety related function. . If the fluid bging processed is radioactive due to leakage from primary" to secondary, the system has the effect of concentrating the activity in the regeneration waste which is processed by the Waste Management System. Failure of any component could compromise the system operation, but would not affect any safety related equipment or prevent safe shutdown of the plant. I This change .does not increase ,the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
Reference:
Table 10.4.6"3 MEM/HO"8802260/Page 12/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-002461, Steam Generator Blow Down (SGBD) System Improvements Functional actuators 'nSummar 'This SGBD valves modification replaced the air-to-open/air-to-close 2BD-VllSA-l,'BD-V15SA'-1, and 2BD-V19SA"1, with an air-to-open/spring-to-close type with the intent of providing a more reliable actuator. The previous actuators relied .on !an. air accumulator to close. The replacement actuators '.,will open ."and., close at rates slower. than. the previous
~ design but will close within current Technical, Specification limits (60 seconds).
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This, modification also installed manual ,gate valves,, (2BD-,V115SN-, 1, 2BD-V116SN-1, 2BD-V117SN-1, 2BD-V118SN-1, 2BD-V119SN-1, ~ and 2BD-V120SN-1) at
- ,the steam generator 'nogzles with the intent .of providing ppsitive isolation
. (while the steam generators, are pressurized) of blowdown to allow for the performance of maintenance of downstream valves. '
I original specification which requires IEEE (containment service) and seismic Category I qualification. The springs on the actuator have been specified to close the valve under maximum system design differential pressures'he valve actuator will Tail'afe on loss of instrument air. The closure under accident cond'itions is still done'y the use of a solenoid valve. Because of- the
'bove, there is no reduction of the valves ability to close and stay closed all expected conditions. 'nder.
The valve stroke Cime has been ,increased 'o minimize the system's susceptibility to column separation during closure and rapid bubble formation followed by condensation-induced water hammers during valve opening following long periods of system shutdown. However, the new closure times are well within the Technical Specification 60-second limit.
Isolation valves have been installed in the blowdown lines at the steam generator blowdown nozzles to allow maintenance on downstream valves. These valves are designed to ASME B&PV Code Section III and seismic Category I which is the same design criteria used for the original design of the line. A failure of, the added valves would not introduce a new accident scenario or a more limiting break in the steam generator. The limiting failure would be a feedwater break between the steam generator and the first check valve, and it has been shown in FSAR .15.2.8 that for this feedwater break, the Auxiliary Feedwater (AFM) system capacity is adequate to prevent uncovering the reactor core. Therefore, a line break in the steam generator blowdown system will not result in an event which would prevent the safe shutdown of the reactor.
MEM/H0-8802260/Page 13/OS1
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
FSAR References. Figure 10.1.0-6
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MEM/HO-8802260/Page 14/OS1
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
't Title.'CR-002543, AMSAC Modificatibn Functional Summar 'This modification adds new cables and equipment utilized as part of the ATWS Mitigation System (AMSAC) Actuation Circuitry. The addition of this equipment to the plant also requires an FSAR change to the Fire Hazard Analysis Appendix,9.5A.
approved by the NRC in a Safety Evaluation Report dated July 14, 1988.
Appendix 'R requires cables considered necessary for safe shutdown to: be analyzed to .ensure that. at least 'ne . train of safe shutdown equipment is available to achieve. cold shutdown in 7g.'hours. New cables 11974S and 99175Q, were analyzed in accordance with the requirements of Appendix R and their routes in the Cable Spread Rooms A and 'B were in compliance with the Appendix R separation requirements. The cables also terminate in "ISOL CAB 2A-2A2-SA; 2B-2B2-SB and ARP-19 SA and SB located .on elevation 305. The HNP Safe Shutdown Analysis identifies that the plant design has.been reviewed to assure that instrumentation and controls for at least one shutdown division of each system, including the necessary support equipment, is, available during shutdown at the alternative locations., 'fherefore, hoss of the cables on El.evation 305 will not impact the capability to 'safely shutdown the plant, from alternative shutdown locations as previously 'analyzed. 'n case of fire. on Elevation 305 requiring control'oom evacuation, HNP procedure AOP-004, Safe Shutdown in Case of Fire or Control Room Inaccessibility, provides shutdown stgps from alterpative loc'ations. Upon transfer to the Auxiliary 'Control Panel ('ACP) the automatic function of these cables will be disconnected to prevent a spurious signal.
It This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than. already evaluated in the FSAR. Thus, no unreviewed safety Question exists'SAR Reference".Section 9.5A, Figure 7.3.1-1 MEM/HO-8802260/Page 15/OSl
CHANGE TO FACILITY AS DESCRIBED. IN THE FSAR Title'. PCR-002869, Emergency Diesel Generator (EDG) 1B-SB Right Bank Intercooler Functional Summar . This plant modification provided a flexible connector for EDG 1B-SB right bank intercooler adapter at the point the adapter connects to the turbocharger. The previous intercooler adapter consisted of a 12" diameter pipe welded to- a "box",constructed=. of "steel platei This adapter connected the turbocharger to the intercooler. The adapter had developed a crack at the weld connecting the.12" pipe and the "box". The crack is thought to have been caused by vibration during EDG operation.
~ supplier and a utilitywho 'had had similar problems with their joint, clamp, backing ring, and bolting material are all of materials EDGs.'he'lexible compatible with the existing EDG. The flexible joint is made -of a
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viton/fiberglass 'material, the clamps are plated malleable iron, the backing unjoint.is galvanized ring metal, and the bolting material is carbon'teel. Based on discussions with the EDG manufacturer and the Turbocharger manufacturer, these materials should withstand the maximum temperature and pressure the flexible should experiehce during operation.
1 The FSAR requi,res the controlled use of combustible materials in the permane'nt plant structure. The use of the flexible material at the location specified.
in PCR"002869 has been reviewed and is found acceptable.
This change does not increase the probability or 'consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated 1n the FSAR. Thus, no unreviewed safety'uestion exists FSAR Referenceections 9.$ .1 and 9.5A MEM/HO-8802260/Page .16/OS1
CHANGE TO FACILITY. AS DESCRIBED IN THE FSAR
Title:
PCR-002878, Emergency Service Water (ESW) Pump Seal Water Supply Functional Summar '. This plant modification deleted the ESW Pump Seal Water Booster system (i.e., pumps 1A-NNS and 1B-NNS, associated valves and piping). The system was originally designed to provide non-operating ESW pump
, seal water. The pump'vendor recommended .seal water flow of 2 gpm even during non-operating conditions such that' no accumulation of dirt or debris will exist during the start of the pumps'his function is not essential for an emergency start of the ESW pumps.
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justified primarily by the capability of the Screen Wash Pump path to supply
.the recommended flow with the screen wash pumps idle.,'The deletion of the ~ ~
pipe, v'alves, and pumps lessens the" number of items 'that can fail and .
therefore lowers the probability of overall failure. The modification also deletes the non-isolable cross'onnect; between ESW Pumps "A" and "B". This alone was determined to create a'n unreviewed safety question under Engineering Evaluation PCR-002848 because it,violated the FSAR statement 9.2.1.3.1. which of cooling under any passive or active failure. The called for assur'ance modification brings the system into compliance with this statement.
o Engineering Perfbrmance Test .101T showed'. that under the lowest normal operating header pressures, the pressure from the Normal. Service Wa'ter System provided flow to the ESW pump bearings of 2.5 gpm and 2.1 gpm to pumps "A" and "B" respectively. This is within the requirements set forth by the pump vendor. (Hayward Tyler-Pump Company). This confirms that an Emergency Service Water Pump will maintain the same amount of reliability as in .the previous configuration, -without compromise to the cross connected system and the overall ESW system reliability.,
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
Reference:
Figure 9.2.1-1 MEM/HO-8802260/Page 17/OS1
'CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title.'PCR-002992, Boron Injection Tank (BIT) Bypass Line Elimination Function Summar '. This plant modification deleted the BIT'ypass line.
Originally the design for the safety injection system required a BIT containing concentrated Boric Acid Solution (12X Boric Acid vs. 4X in Normal Reactor Coolant). 'fter injection'f this concentrated solution'nto the RCS, the safety injection lines required: flushing to ensure a uniform Boric Acid Concentration. The BIT bypass .line provided this capability. However, prior to issuance of the SHNPP operating license, CPSL demonstrated to the NRC that the BIT no longer required a concentrated Boric Acid Solution. Therefore, the safety injection system lines no longer require flushing after injection through the BIT, and the BIT bypass line 'can be isolated or .deleted without
.effect on system or plant operation,.
"1 cracking of .RCS piping due to thermal cycling caused by leakage of relatively cold water through closed isolation valves. At SHNPP, the BIT bypass line isolation valve had been confirmed to be leaking.. This leakage created the same situation in the cold leg injection lines which resulted in fatigue cracking of RCS. piping at other plants. The BIT bypass line is no longer required for operation of the safety injection system. Therefore, to eliminate this source of leaka'ge permanently, the BIT bypass line was deleted entirelg. The ,remaini'ng branch connections at the main headers are now capped.
Based on the above, deletion of the BIT bypass line does not 'increase the probability or consequences of analyzed accidents, nor intr'oduce a different type'f accident or equipment malfunction than'lready evaluhted in the FSAR. Thus, no unreViewed safety question exists.
Reference:
Figure 6.3.2-01, Table 16.3-5 MEM/HO-8802260/Page 18/OSl
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title.'PCR-003022, Delete Post-Accident Access Area Monitor in Turbine Building Functional Summar '. This plant modification removed post-accident access area radiation monitors Systemsin the RM-01TR-3515A and RM-01TR-3516A which were located instrument and service air compressor area- of the Turbine Building,'.elevation 261' This action'as initiated by t;he site Radiation Moni'toring (RMS) force in an effort to reduce the number of area monitors in the system. 'ask safety related portion of 'he RMS and are not included in Technical
~ Specifications; Review of FSAR figure 12.3A-4 (Post.-A'ccident Dose Rates and
~
Accessibility Analysis), and Reg ,Guide 1.97 Table 3 (Type E Variables),
concluded that RM-01TR-3515A and RM-'01TR-3516A were not require'd in their previous location and, therefore, were deleted. Removal of these area monitors does not. in any way facilitate the release of radioactivity. These monitors are not discussed in the Technical Specifications. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased. The probability for an, accident or malfunction'f a different type than an/
evaluated previously in the FSAR has not been created. Thus, no unreviewed safety question exists..
~
Reference:
Section 12.3.4.1.8.4 MEM/HO-8802260/Page 19/OSl
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title.'PCR"003074, Spare Penetration Modification for Sludge Lance and Eddy Current Lines Functional spare Summar .'his plant modification changed'he containment penetration .S-66 such that it configuration of can be more readily used during outages. The original design of .penetration S"66 utilized a 10" diameter welded cap on .the inside of the containment building. This change outfitted the penetration .'ith flan'ged connections on both'ides of the containment wall. During 'outages, the sleeve is used for eddy current, sludge lancing and other equipment Chat must 'e'un from outside the containment building to a,location inside. During operations the blind flanges constitute
'the containment barri'er -and, during outages vapor seals. pr'oxide protectidn
"'gainst. refueling accidents.. A test connection has been provided such that LLRT requirements can be 'satisfied during operation. ~
4 configuration is mechanically equivalent to the previous design. The previous design 'utilized a 10" diam. welded cap on the inside of the containment building. This was the mechanical boundary between the containment atmosphere and the RAB. The new configuration merely removes the welded.cap and replaces it with 10" diam. flanges and" blind"flanges. The'langes are, rated for . the same pressures that the cap was originally designed for. This modification is essentially a replacement with an equal to or better component and hence as so .
can be considered equally safe and containment integrity is maintained. This also negates any increase in,probability for the release of radioac'tivity.
I I
This change does not increase the probability or cdnsequences of analyzed accidents, nor introduce a different type of .accident equipment malfunction
'han already 'evaluated in the FSAR. Thus, no unreviewed safety question exists ~
FSAR Reference'Sections 6.2.4, 6.2.6, 3.8.2 MEM/HO-8802260/Page 20/OS1
CHANCE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-003311, Addition/Relocation of Level Components for Moisture Separator Drain Tanks (MSDT's)
Functional Summar . This plant modifi'cation installed new level gauges on the moisture separator drain tanks'A & 1B. In addition, the associated level switches are relocated - and the set points revised to reflect the new locations. The, newly installed equipment has also been heat traced for freeze protection.
Relocation of the level switches will allow a wider range of operation for the MPDT's while retaining the loop seal to Feedwater Heater No. 4. Also, the installation of new 1'evel gauges will. provide. the ability to monitor the new.
level in the MSDT's. ~ ~
mitigation of any design basis accident.. This change does not, increase the, probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists. ~
FSAR Reference'Figure 10.1.0-5 MEM/H0-8802260/Page 21/OSl
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PCR-003509, Auxiliary Feedwater (AFW) Drip Leg Drain Line Reroute Functional Summar . This plant modification reroutes the drip leg drain line off of the Turbine Driven AFW Pump from the condenser and 'connects it to the blowdown line 6BD10-68-1 which is vented to the atmosphere. In the previous configuration, when work- was being performed on the condenser, the drip leg had to be isolated. With the drip leg isolated;".the steam traps in the drain line:could not handle the build up of condensate, and the Turbine Driven AFW Pump could trip on overspeed when started due to water slugging.
the availability or reliability of the 'DAFW Pump, but Vill make it more
,reliable 'by eliminating the water slugging potential. By the deletion of this line to the condenser, the potential of air inleakage to thh condenser is reduced. ~ The additional line to the blowdown,system will have no adverse effect on that system. - ~ ~
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. . Thus, no unreviewed safety questi'on exists'SAR
Reference:
Figure 10.1.0-1 and 10.1.0-6 MEM/H0-8802260/Page 22/OS1
'HANGE TO FACILITY AS DESCRIBED IN THE FSAR Title. PCR-003550, Steam Generator Drain Line Repair Functional Summar '. This modification was made to the three steam generators (SG) primary head drain line piping. During August 1988, while in a refueling outage, an accumulation of residue (appearing to be. boric acid crystals) was observed on SG'z A and B. It, was concluded that the residue was a result of reactor coolant system leakage and a repair was necessary. The SG repair consists of cutting off the channel head drain tube (leaving a short alignment protursion) and welding a new Irfconel nozzle onto the channel head. This new nozzle (W drain pipe socket) surrounds the existing channel head hoLe,and captures the lower end of, the., original drain tube. The new nozzle welded to the . outside surface of 'the. channel head thereby is,'ppropriately enclosing the hole origihally drilled through the channel head. This ensures that any .leakage through the hole, 'or tube, is contained within the new metal
~
boundary. h Following attachment of the new drain pipe socket, the existing valve and piping assembly was reinstalled.
and is considered to provide a greater margin .of safety. The new dragon pipe sock'et is made of Inconel (ASME SB-168) material and is compatible with reactor'oolant fluid; and is compatible with the original valve and piping assembly which was reused. The n'w drain pipe socket was designed and analyzed by Westinghouse and satisfies the requirements of the SG design specification.
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR ~ Thus, no unreviewed safety question exists.
FSAR Reference. 'Figure 5.1.2-1 MEM/HO"8802260/Page 23/OSl
CHANGE TO FACILITY AS DESCRIBED IN THE FSAR
Title:
PGS-003606, Steam Generator Slowdown (SGBD) Settling Tank Piping Wall Thinning Functional Summar . This plant modification replaced the Steam Generator Blowdown System magnetic filter settling tank pump discharge piping (previously carbon steel) from the pump discharge flanges to the Spcondary Waste System Discharge Header. 7WS6-63-1.. The replacement piping is stainless steel. The modification also replaces the A and B settling tank pump Discharge Valves IBD-119 and IBD-122 and Discharge Check Valves 1BD-120 and
'1BD-123, respectively, with stainless steel bodies. The modification also replaces the settling hank pumps'inimum recirculation piping,, the flow orifices, and; Isola'tion Valve 1BD-124. ',
I
~ I a ' e e The valves. and piping were replaced with >stainless steel to prevent against corrosive attack from secondary waste water that can back flow into the
. settling tank pump discharge piping during condensate pdlfsher regeneration..
This event has occurred on at least one occasion and resulted in severe corrosion to the settling tank pump and associated discharge piping and valves.
The settl:ing tank pump discharge piping was previously a c'omb'inatjon of 1<"
and 3" (nominal) pipe. The 1<" piping has been up-sized t'o 2" t'o accommodate larger .valves and the 3" section pi11 remain as is 'with only a material change.
This modification also installs a new manual Isolation Valve 1BD-161 at the steam generator blowdown/secondary waste interface. This was installed to facilitate the recoVery of the secondary waste header while the settling tank piping modifications were being performed 'and to facilitate the maintenance valves 1BD-120 and 1BD-123 located upstream. of'heck pressure boundary, etc. cannot challenge steam generator inventory through scenario since blowdown flow is regulated by physically separate, any'redible safety"related components located upstream in the RAB. A failure of the pressure boundary would cause the Turbine Building Elevation 240'o be filled with steam', however, it would not be considered an initiating event due to the arguments stated above. Although a failure of the'ett1ing tank or its associated piping, components, etc., is credible, it would not affect the safe shutdown of the plant because a blowdown pressure boundary failure is .bounded by more limiting events which have greater consequences and much higher probability of occurrence.
This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus, no unreviewed safety question exists.
FSAR Reference'. Figure 10.1.0-6 MEM/H0-8802260/Page 24/OS1