ML19340B441
| ML19340B441 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/30/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8011100485 | |
| Download: ML19340B441 (43) | |
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I At:bama Pow:r Company 600 North 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 250-1000 m
F. L. CLAYTON, JR.
Alabama Power sen.or vice President ev souven ewnc sa -
4 October 30, 1980 5
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NS C
m' 30 NRC IE Bulleti 79-01B GG Docket No. 5 -348 3
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Mr. James P. O'Reilly "i
U. S. Nuclear Regulatory Commission Region II Suite 3100 101 Marietta Street N. W.
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
re Enclosed is additional information on Farley Nuclear Plant Unit'l concerning environmental qualification of electrical equipment. Th17 report, together with the response to IEB 79-01B dated July 30, 1980,'
provides the complete information required by the Order for Modification of License dated September 19, 1980, including requirements as clarified in IEB 79-01B Supplements 1, 2 and 3.
Specifically, this submittal
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addresses:
- Acceptability of equipment qualification inside containment in light of the revised steam line break analysis for Farley.
- Outstanding items with justifications for interim operation.
- Several clarifications to the original response.
The enclosed package constitutes a revision to the July 30 submittal and the pages are to be inserted in accordance with the instructions provided with the enclosure.
UFFICIAL OOPY Yr5~
8011100
Mr. James P. O'Reilly, Director October 30, 1980 U. S. Nuclear Regulatory Commission Page 2 If you have any questions, please advise.
Yours very truly, g
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N"I F.
. Clayton Jr.
TLC /rt Enclosure SWORN TO AND SUBSCRIBED BEFORE ME THISJZf A DAY OF cc: Mr. R. A. Thomas gefA
,1980.
Mr. G. F. Trowbridge Office of I & E Div. of Reactor Operations Inspection
_J g Washington, D. C.
m/s' v=,
R. W Mr. S. A. Varga er Notary Public Dr. Z. Rosztoczy 4
Mr. W. H. Bradford My Commission Expires:
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REVISION PACKAGE INSTRUCTIONS - REVISION 1
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The Alabama Power Company Response to IES 79-OlB dated July 30, 1980, j
j was provided in a ring binder with each section separated by index tabs.
l The enclosed package contains three complete sections and a number of individual pages which are to be inserted into this binder as follows:
a i
1.
Insert revised Section B.1.
Discard old Section B.1.
2.
Insert revised Section C.I.
Discard old Section C.1.
E 3.
Insert new Section D.
4.
Insert revised table of contents. Discard old table of contents.
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5.
For the following component worksheets, insert the revised sheet in in the appropriate subsection and discard the old worksheet:
- Section C.2.2 Sheets 2 and 3
- Section C.2.3 Sheets 6 - 8 i
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- Section C.2.4 Sheets 25 - 33
- Section C.2.13 Sheets 53 - 55 i
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Revised Section 3.1 l
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SECTION B.1 DIS"CUSSION OF THE MASTER LIST The Master List has been developed by reviewing the FSAR, technical specifications, emergency operating procedures and P&ID's of the safety related systems in the plant. A discussion of the safety systems and features reviewed is given below.
Each P&ID is systematically reviewed taking into consideration which accidents the system is required to mitigate / monitor and if the system is exposed to the harsh environment created by the accident.
If a component is used to mitigate / monitor an accident, but not exposed to the accident environment, it is not included in the Master List.
Following is a description of the environ = ental zones and general comments concerning systems evaluated as part of the IEB 79-01B review.
ENVIRONMENTAL ZONES
- 1) INSIDE CONTAINMENT During a LOCA, the harsh environmental parameters of high temperatu*e and high pressure are limited to the containment. Initially, the evaluations for temperature and pressure inside containment were both based on the LOCA environment which was determined in the Farley FSAR accident profile calculations to be more limiting than a steam line or feedwater line break with automatic spray actuation.
This is reflected on the component worksheets for all components inside the containment.
However, due to the condensation phenomena that was identified in the NRC model for calculating steam line break ervironment which was not con-sidered in the Farley FSAR MSLB accident profile calculations, the MSLB 1
Rev. 1
environment was recalculated with resulting temperatures higher than previously calculated. The evaluation for temperature inside containment is now based on the MSLB environment which is now more limiting than the LOCA environment.
A transient MSLB containment thermal analysis was performed (for the worst case of the spectrum of breaks) for each type of Class 1E component inside containment to determine the peak co=ponent surface temperatures.
The methodology used to calculate the temperatures was based on the NRC staff's approved assumptions discussed in Appendix B of NUREG-0588. These analyses show that the peak surface temperatures resulting from the MSLB environ =ent do not exceed the qualification temperature for each type of ce=ponent inside containment.
Table B.1-1 su=marizes the results of these analyses.
- 2) OUTSIDE CONTAINMENT Pressure and temperature parameters are considered for the main steam room which is the only area outside containment subject to an HELB and containing components required to mitigate the accident.
For LOCA conditions, Class lE equipment outside the containment was evaluated for radiation exposure based on the proximity of the equip-to piping systems carrying recirculated containment sump fluids.
ment The source term used in producing the dose rates calculated in our analysis includes 50% halogens, 1% fuel, and the RCS inventory diluted by the safety injection accumulator tanks and the RWST. The noble i
gasses are not included in the source term, since nonpressurized undiluted reactor coolant is recirculated outside the containment under accident or post-accident conditions.
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2 Rev. 1
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ENGINEERED SAFEGUARDS ACTUATION All devices required for engineered safeguards initiation that are subject to a harsh environment are included in the Master List. The L
i processors of the signals (logic cabinets) are not included since they j
are located in the control room or cable spreading room and are not j
subject to the harsh environment.
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REACTOR PROTECTION I
Included for evaluation are the tecperature elements (TE's) on the RCS i
RTD loop required forsO6T/Tavg protection signal, hot and cold leg TE's to the temperature recorded and the protection grade pressure j
transmitters on the pressurizer. The wide range pressure transmitters are alto included for evaluation, as well as steam generator level.
CONTAINMENT ISOLATION Containment isolation valves located inside containment close shortly after the accident occurs and are included in the Master List under the appropriate systems in which they are installed.
Containment isolation valves located outside containment close shortly after the accident occurs and are not exposed to the containment atmosphere. Therefore, they are not listed.
MAIN AND AUXILIARY STEAM LINE ISOLATION The main steam line isolation and break protection system is included in I
the Master List for the effects of a steam line break. The pressure and and temperature profiles are presented in Section C.3.
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MAIN AND AUXILIARY FEEDWATER ISOLATION 1
I For a main feedwater line break, the harsh environment is conservatively i
considered to be the same as a main steam line break.
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EMERGENCY POWER i
The Emergency Diesel Generators, 4 KV Switchgear, 600 Volt Load Centers, MCC's, and DC systems are not included as they are not subjected to the harsh environment of the high energy line break.
HIGH HEAD SAFETY INJECTION a
The High Head Safety Injectfon System is not included for evaluation l
since all active components are located outside the containment and not subjected to the harsh environment.
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1 CONTAINMENT HEAT REMOVAL The emergency containment cooler system is included for evaluation. This includes the fan motors and valves in the service water lines.
I The containment spray system is not included for evaluation since all active components are located outside the containment and not subject to the harsh environment.
CONTAINMENT COMBUSTIBLES GAS CONTROL j
Post-LOCA mixing fans and hydrogen dilution fans are included for evaluation.
I AUXILIARY FEEDWATER The auxiliary feedwater systems most severe operating environment is due 4
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to a break in the main steam system, and all components in this area are included in the Master List for evaluation.
CONTAINMENT VENTILATION The containment purge valves inside containment are listed for evaluation to LOCA conditions.
However, the valves outside containment are not included since they are not exposed to the containment post-accident atmosphere.
CONTROL ROOM HABITABILITY SYSTEMS AND VENTILATION FOR AREAS CONTAINING SAFETY RELATED EQUIPMENT This equipment is located in auxiliary building areas and not subject to h21sh environmental conditions and is, therefore, not included for evaluation.
SERVICE WATER This system supplies cooling water to the contain=ent coolers through containment isolation M0V's located in the containment which would be epxosed to an in-containment accident environment.
These MOV's have been included in the Master List for evaluation.
ACCUMULATORS The accumulators are passive components, discharging into the RCS cold i
legs through normally open motor operated valves when the reactor coolant system decreases below accumulator pressure.
Since accumulator injection is an automatic mechanical function, and all components associated with the accumulator function are passive, they are not included in the Master List.
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PRESSURIZER SPRAY l
Components associated with pressurizer spray are not included in the Master l
List since they are not required to achieve hot shutdown as discussed i
j under " Emergency Shutdown."
l SAFETY RELATED DISPLAY INFORMATION i
All of the required post-accident display instrumentation is located in the control room which is not subject to a harsh environment. Therefore, they are not included in the Master List.
EMERGENCY SHUTDOW J
The emergency shutdown systems listed in Bulletin 79-OlB (Appendix A) vere reviewed and inc.luded in the Master List in accordance with their operation as required in the Farley FSAR.
Shutdewn is addressed within the f r amework of the Farley licensing commitments, as summarized in our response to NRC question 210.3 submitted under cover of our letter dated September 22, 1980, to Mr. A. Schwencer of the NRC.
Equipment required to achieve hot shutdown following an accident is included in the Master List.
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POST-ACCIDENT MONITORING Components required by the Emergency Operating Procedures for post-accident monitoring and which may be exposed to the harsh environment are included in the Master List for evaluation.
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MAIM STEAM ATMOSPHERIC RELIEF VALVES A design change (PCN 79-564) has been issued to provide a more reliable control capability for the atmospheric relief valres in the event of a line break in the main steam room. This design change includes the addition of a solenoid valve and a stem mounted limit switch on each valve. These components will be environmentally qualified since they are to be located in the main steam room.
This design change is scheduled 1
for implementation during the second refueling outage.
PORV's The pressurizer PORV's are TMI action plan equipment and will be addressed later.
7 Rev. 1
TABLE B.1-1 Peak Equipment Surface Temperatures Resulting from a MSLB Inside Containment MAXIMUM CALCULATED QUALIFICATION COMPONENT SURFACE TEMPERATURE TEMPERATURE COMMENTS RTD 3550F 4300F note 2, 3 Electrical Penetrations 3050F 340 F note 1, 3 0
Terminal Block (Junction Box) 301 F 307 F note 1, 3 0
Cables - Instrumentation 2700F 340 F note 1, 4 Control and Power 2700F 324 F note 1, 4 Solenoid Valves 324 F 340 F note 1, 3 Limit Switches 3050F 340 F note 1, 3 Level Transmitters 3550F 3800F note 2, 3 Motor Operated Globe and 2700F 3150F note 1, 4 Cate Valves A.C. Motors -
280 F 300 F note 1, 3 Containment Air Cooler Fan Motor Hydrogen Mixing Fan Motor Dilution Fan Motor Flow Transmitters 355 F 380 F note 2, 3 0
1 Differential Pressure Transmitters 2700F 320 F note 1, 4 NOTES 1.
Maximum surface temperature of this component resulting from a MSLB is calculated using the methodology presented in Appendix B of NUREG 0588.
2.
This component is qualified in excess of the peak containment vapor temperature calculated using the methodology presented in Appendix B of NUREG 0588.
Since the component surface temperature cannot exceed the peak vapor temperature, this peak vapor temperature is reported as the component's peak surface temperature.
Rm R
NOTES (CONTINUED) 3.
The MSLB which produces the highest surface temperature for this component is the 0.681 ft2 split rupture at 70% power.
4.
The MSLB which produces the highest surface temperature for this component is the 0.7065 ft2 split rupture at 30% power.
GENERAL The highest component surface temperature is reported in this table.
To establish this temperature the integrated heat flux to the component is maximized.
This is done by analyzing various geometries, materials and material thickness, various configurations and flow directions over the component, as well as various component sizes.
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SECTION C.1 DISCUSSION Of CGd.PONEhT EVALUATION WORK SEEETS 1~.
The component evaluation sheets are formated in accordance with the sample in IE Bulletin 79-01B.
2.
A cocponent evaluation sheet has been prepared for every line item in the Master List.
A component evaluation sheet has been prepared for each line item on the Master List. Each Section of the ce=ponent evaluation sheets corresponds to a specific plant systec.
3.
The cocponent evaluations have been based on an extensive research of the qualification documents. Where qualification docu=ents were not available, evaluations were made by engineering analysis of the co=ponent materials.
Where necessary, vendor inforcation was obtained in preparing the engineering analysis.
4 For all devices, both in-containment and outside, the manufacturer, model number, location, area and floor elevation were based on ngineering documents.
The information vill be verified on a sa ple basis during a valkdown at the next urf_,efueling.
S.
Flood elevation was considered for equipment located both inside and outside the contain=ent.
The elevation indicated on the cocponent evaluation sheets for in-contain=ent equipment represents the probable maximum flood level based on the RCS inventory, the SI accumulators and the RWST emptying into the containment.
As discussed in the FSAR, Section 3K.4.1.2.7, the vorst case flooding concern is a main feedline break.
Flooding in the main steam room due to a main feedline break is limited by automatic controls, to a level of 3'-5" above the floor.
This level is well below the lowest safety related equipment.
For this reason, flooding was not included on cocponent evaluation worksheets for equipment outside the containment.
C.1-1
6.
As stated in the " Discussion of Master List," all devices in the auxiliary building have been evaluated for radiation resistance only for an accident inside containment (recirculation of containment sump liquid). Temperature, pressure and humidity outside HELB areas are considered no worse than that during a normal unit shutdewn. The
" Discussion of Master Li,st" identifies the High Energy Line Breaks (EELB) in the Auxiliary Building.
The radiation dose levels in the auxiliary building for a post in-containment accident are based on calculations developed for response to "NUREG 0578 Short Term Requirements," Item 2.1.6.b (" Plant Shielding Review"). Radiation qualification requirements were not specified for all equipment bought for outside containment use. However, based on the available data and engineering analysis, all the equipment has been evaluated for the radiation levels, and all found acceptable. A su==ary of these calculations is presented in Section C.3.
7.
Where noted in the 'Tnvironmental Qualification" colu=n of the co=ponent evaluation sheet, the NSSS vendor's proprietary information has not been entered. However, a reference is made to the document where the information can be found. An independent evaluation was performed on these doeurents to assure qualification for the specified accident environment.
8.
The Document References are listed in Section C.4 and will be available at Farley Nucleat Plant Document Control.
9.
The environmental parameters listed in the " Spec." colu=n under
" Environment" correspond to the accident conditions stated in the FSAR.
These values equal. or exceed those set forth in the Enclosure (4) Guidelines of IE Bulletin 79.01B, and encompass the equipment qualification parameters appropriate for the spectrum of LOCA's and HELB's. For the limiting main steam line break, thermal responses of safety-related components were calculated using the methods presented in NUREG 0588 and were used to establish the required qualification parameters.
10.
For equipment whose safety related function is performed within a i
short time into an event, a minimum of one hour was assumed to be the specified operating' time, even though the actual specified operating I
time is indicated on the evaluation work sheets, which may be considerably less than one hour.
11.
Unless otherwise specifically stated t:> the contrary, the time dependent temperature and pressure qualification profiles envelop the specified l
l or required profiles for each equipm.c.nt or component for which a work-sheet is provided. The qualification profiles are contained in the reports referenced in Section C.4 dn either graphic or tabular form.
12.
Where the words " sequential test" are used to describe the qual!.fication method, it is meant that ele =et)E's of the test were performed in steps or sequence. In some cases, ay'.ng was performed before irradiation, and vice versa. In all cases, irradiation and aging were perforced before exposing the test speciten to the accident profile. The words
" simultaneous test" mean that the test parameters were applied at the same time, or simultaneously.
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j SECTION D S'MtARY OF OUTSTANDING ITEMS l
As a result of the IEB 79-01B qualification review, some components were determined to be deficient in qualification documentation.
These generic types are solenoid valves, bo'th inside and outside the containment, and limit switches outside the containment.
These deficiencies, together with corrective action commitments and justification for interim operation, are given below.
1.
Solenoid Valves - Inside Containment A total of 29 solenoid valves inside the containment were determined not to have adequate qualification documentation. These solenoid valves are used on containment isolation valves and perform their 3
safety function prior to the effects due to the accident environment.
Should failure occur, the isolation function of these valves would be maintained and such failure would not adversely affect other safety-related equipment. Furthermore, these solenoid valves have high temperature coils and contain no Buna-N or plastic parts.
Although 4
complete qualification testing or analyses have not been performed on the specific assemblies, separate qualification tests have been performed on individual constituent components of the valve assembly.
Based on the fact that no materials which have deleterious effects da to the harsh environments are included in the valves, and that previous limited testing has successfully verified qualification, interim use of these valves is acceptable until they can be replaced. Replacement with qualified valves having adequate documentation will be completed by the end of the third refueling outage.
If problems arise beyond j
the control of Alabama Power Company which may impact this schedule,
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the NRC will be notified. A replacement program to - fully support this I
j schedule has been implemented.
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- 2. _S,olenoid Valves - Outside Containment A total of 43 solenoid valves outside the contai nment were detcrmined I
not to have adequate qualification documentation Although a few of these valvis do contain plastic seals i
, interim operation can be i
justified on the basis that the accident temp erature excursion for a main steam line break lasts less thar. two seconds 1
sufficient
, and there is
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thermal lag within the valve body to preclud t
to the valve internals.
e any damage In addition, the valves have high temperature coils, which would resist damage due to temperatur short duration.
e excursions of The pressure excursion is so low and so short a i
i be negligible.
s to Based on the fact that the short duration of th e harsh environment would have no deleterious effect on these j
solenoid valves, interim use of these valves is acceptabl I
e until they can be replaced.
Replacement with qualified valves having adequ t s'
a e documentation will be completed by the end of the third refueling outage If problems arise 4
beyond the control of Alabama Power Company whi h c may impact this schedule, the NRC will be notified.
A replacement program to fully support this schedule has been implemented.
I 3.
Limit Switches - Outside Containment A total of 36 limit switches outside the containment were determined not to have qualification docceentation.
Interim operation is justified on the basis that the accident temper ature excursion to which these switches are exposed is less than two seconds in duration, and the thermal lag of the switch enclosure precludes d t
amage to the internals.
Should failure occur subsequently, other safety r l e ated components would not be affected.
{
Based on the facts of short duration of the harsh i
environment and that potential subsequent failure will not adversely 2
Rev. 1
affect other safety-related equipment, interim use of these switches is acceptable until they can be replaced.
Replacement with qualified switches having adequate documentation will be completed by the end of the third refuleing outage.
If any problems arise beyond the control of Alabama Power Company which may impact this schedule, the NRC will be notified. A replacement program to fully support this schedule has been implemented.
NOTE:
It is anticipated that the third refueling outage will not extend beyond June 1982.
4 Revised Table of Contents
ALABAMA POWER COMPANY J. M. FARLEY NUCLEAR PLANT UNIT 1 DOCKET:
50-348 RESPONSE TO IE BULLETIN 79-01B TABLE OF CONTENTS A.
List of Systems Included in the Master List B.
Master List of Syste= Components Required to Function for LOCA/HELB Accident B.1 Discussion of the Master List B.2 Master List of System Components C.
System Component Evaluation Work Sheets C.1 Discussion of System Component Evaluation Work Sheets C.2 System Co=ponent Evaluation Work Sheets for Components Listed in Master List C.2.1 Reactor Coolant Instrumentation C.2.2 Reactor Coolant - Stea= Generator C.2.3 Reactor Coolant System - Pressurizer C.2.4 Feedwater Control System C.2.5 Safeguard Systems, RHR/LHSI C.2.6 Containment Cooling and Purge C.2.7 Hydrogen Recombiner System C.2.8 Containment Post-LOCA Air Mixing System C.2.9 Chemical and Volume control / Safety Injection C.2.1C
'- ; Cavity Post-LOCA Dilution System C.2.11 Post Accident Containment Combustible Gas Control C.2.12 Liquid Waste Disposal System
... _. = _._
i C.2.13 Main Steam C.2.14 Auxiliary Steam 3
i, C.2.15 Main Feedwater and Condensate 1
C.2.16 Auxiliary Feedwater C.2.17 Chemical Injection System C.2.18 Sampling System 4
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C.2.19 Service Water
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C.2.20 Component Cooling Water J
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C.3 Su==ary of Radiation Exposure Outside Containment C.4 List of Qualification Document References and Accident Profiles D.
Su==ary of Outstanding Ite=s f
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l IE BULLETIN 79-01B RESPONSE This response covers Action Ite=s 1 through 5 of the USNRC cover letter to IE Bulletin 79-01B dated January 14, 1980. This document includes the following:
Section A: List of systems included in the Master List for evaluation.
Section B: Master list of components which are required to mitigate a postulated accident or monitor post-accident conditions. Only the components in the accident environment are included.
Section C: Component evaluation worksheets which provide information on the environmental qualifications available for the cocponents covered in Section B.
Section D:
Su==ary of outstanding items along with justification for interim operation.
Sections B and C include discussions on the basis for the Master List and Component Evaluation worksheets, respectively.
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Joseph M. Ft.cy Nucl:ar PI:nt Unit 1
SECTION C.2.2 Sheet 2 of ENVIR NMENT DJCUMENTATION ilEF.
EOUIPMENT DESCRIPTION QUAL OUTSTANDING PA R AMET E R SPEC.
QUAL.
SPEC.*
QUAL.
METHOD ITEMS SYSTEM:
Reactor Coolant OPE A ING Irji-5 min.
Trip-5 min.
PLANT ID NO.
N1B21FT402 4 months 4 months COMPONENT:
Pressure Transmitter TEMP.
300
("F )
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PRESSURE 62.2 (PSIA)
Note 2 Note 3 3
i Note 3 None MDOEL NUMBER:
763 RELATIVE IlUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Post Accident Monitor CllEMICAL ll B0 H B0 3 3 3 3 SPRAY
+ Na0li
+Na0ll 4
1 Note 3 None
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10% for <5 min.
ACCURACY: SPEC:
25%,5 min.--4 mos.
- =5x 107 DEMON: Note 3 RADIATION Rads Note 3 4
i Note 3 None (1 = Note 5 SERVICE:
LOCATION: Containment El 116, N te N e No e 4 Note 6 Note 6 None FLOOD LEVEL ELEV:
115' SUBMER-k ABOVE FLOOD LEVEL: Yes GENCF N/A N/A N/A N/A N/A N/A k
3
- DOCUMENTATION
REFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse r mp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to 1120F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J.M. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
=3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
- 4. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B.
- 5. For 6, the component is considered qualified if the 6 dose of 2 x 100 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been estchlished for Barton transmitters.
An engineering analysic using activation energies and regression curves for the constituent materials will be performed to establish end of life.
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1 234
Aseph M. Farley Nucliar Pirnt Unit 1
SECTION C.2.3 Sheet 6 of ENVIHdNMENT DOCUMENIATION REF.
EQUIPMENT DESCRIPTION QUAL
QUAL.
SPEC.
OVAL METHOD ITEMS SYSTEM: Reactor Coolant OPERATING Trip-5 min.
Trip-5 min.
TIME Post DBE -
Post DBE -
1 1
Note ?
None PLANT 10 NO. Q1B31LT459 4 months 4 months COMPONENT:
Level Transmitter T E MP.
300
("f1 Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PR ESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
764 HELATIVE IlUMll)l T Y (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Level Monitor CllEMICAL H 803 Il 1t03 3
SPHAY
+NaOH 4 Na0ll 4
1 Note 3 None ACCURACY: SPEC:
+25%
6 = 5 x 107 H A0l ATION Rads Note 3 4
1 Note 3 None DEMON: Note 3 8 = Note 5 SERVICE:
PZR Water Level
^
a LOCATION: Containment El 133'-6" Note 4 Note 6 Note 4 Note 6 Note 6 None FLOOD LEVEL ELEV:
115' SUBMER-c.
ABOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A o
- DOCUMENTATION
REFERENCES:
_ NOTES 1
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300"F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to ll2oF in 11.5 days.
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Stoltz (Test) (Westinghouse Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J. H. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
- 3. J. M.
Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
'.. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-018.
- 5. For 8, the component is considered qualifled if the 8 dose of 2 x 10 Rads is reduced by shie? ding to 10% of the 8 dose.
- 6. A qualified life has not been established for Rarton transmitters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. l
Joseph M. Faiiey Nucl:ar Plant Unit 1
SECTION C.2.3 Sheet 7 us ENVIR NMENT DOCUMENTATION REF.
EQUIPMENT DESCRIPTION QUAL OUTSTANDING
'A R A ME TI' R SPEC.
QUAL SPEC.
- UUAL.
METHOD ITEMS SYSTEM: Reactor Coolant OPERATING Trip-5 min.
Trip-5 min.
M m.-
1 1
h3 h
% n r. -
TK PLAN 110 NO. QlB31LT460
. months 4 months COMPONENT:
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON ITT PRESSURE 62.2 (I"ilA)
Note 2 Note 3 3
I Note 3 None MODEL NUMBER:
764 RELATIVE IlUMIDITY (%)
100 Note 3 4
1 Note 3 Nonc FUNCTION:
Level Monitor CllEMICAL 11 1503 II B03 3
3 SPRAY 4 NaOll 4 Na0ll 4
1 Note 3 None 6 = 5 x 107 ACCURACY: SPEC:
125%
RADIATION Rads Note 3 4
1 Note 3 None DEMON: Note 3 6 - Note 5 SERVICE:
PZR Water Level AGING 2
LOCATION: Containment El 133'-6" Note 4 Note 6 Note 4 Note 6 Note 6 None R
FLOOD LEVEL ELEV:
115' SUBMER-n T
ABOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A o
a
'DOCtIMENTATION
REFERENCES:
-NO TES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to 1120F in i1.5 days.
Stoltz (Test) (Westingbouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
,2. J.M. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
.3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference 1 for details.
'4. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B.
- 5. For 6, the component is considered qualified if the 6 dose of 2 x 10 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been established for Barton transmitters. An engineering analysis using activatic,n energies and regression curves for the constituent materials will be performed to establish enel of life.
Rev. I
loseph M. Fml;y Nucl:ar PI:nt Unit i
SECTION C.2.3 Sheet 8
of ENVlfl NMENT DOCUMENTATION REF.
COUIPMENT DESCRIPTION OUAL-OUTSTANDING PA llAME T E R SPEC.
OUAL.
SPEC.
QUAL.
METl10D lTEMS SYSTEM: Reactor Coolant OPERATING Trip-5 min.
Trip-5 min.
PLANT ID NO.
Q1B31LT461 WE Post m-MM-1 1
h3 kne 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTU RE R: BARTON PRESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
764 RELATIVE IIUMIDIT Y (%)
100 Note 3 4
1 Note 3 Hone FUNCTION:
Level Monitor CllEMICAL ll B0 11 B03 3 3 3
SPil AY 4 NaOli 4 NaCll 4
1 Note 3 None ACCURACY: SPEC i2S 6=5x 107 N
3 RADIATION Rads Note 3 4
i Note 3 None 6 = Note 5 SERVICE:
PZR Water Level AGING LOCATION: Containment El 133'-6" Note 4 Note 6 Note 4 Note 6 Note 6 None h
R FLOOD LEVEL ELEV:
115' SUDMER-2 ADOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A (DOCUMENTATION
REFERENCES:
NOTES:
Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to ll20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to J.M. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01n.
- 5. For 6, the component is considered qualified if the 8 dose of 2 x 108 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been established for Barton transmitters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. 1
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1 234
b Joseph M. F. icy Nucl;ar Plant Unit 1
SECTION C.2.4 Sheet 29 cf ENVIRONMENT DOCUMENTATION REF.
EQUIPMENT DESCRIPTION QUAL
QUAL.
SPE C.
- OUAL.
METIIOD ITEMS SYSTEM:
Feedwater Control OPERATING Trip-5 min.
Trip-5 min.
PLANT ID NO.
Q1C22LT485 TIME Post DBE -
Post DBE -
1 I
Note 3 None 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PRESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMDER:
764 RELATIVE llUMIDIT Y (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Feedwater Control CilEMICAL II n0 3 3 II n03 3
SPRAY
~
+Na0li 4 Na0ll 4
1 Note 3 None
+10%,-= f or < 5 min.
6 = 5 x 107 ACCURACY: SPEC:125't for 5 min.-4 Ns DEMON: Note 3 R AOl ATION Rads Note 3 4
I Note 3 None 6 = Note 5 SERVICE:
Stm. Gen. Water Level LOCATION: Containment El. 168e AGING Note 4 Note 6 Note 4 Note 6 Note 6 None R
FLOOD LEVEL ELEV:
115' SUDMER-0 ABOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A j
o
- DOCUMENTATION
REFERENCES:
_ NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 brs.-56 min., and ramp down to ll20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in 1 br.-45 min., ramp down to 2_. J.M. Farley FSAR Figure 6. 2-6 16 psia in 11.5 days.
- 3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
- 4. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B.
- 5. For 6, the component is considered qualified if the 6 dose of 2 x 108 Rads is reduced by shielding to 10% of the 8 dose.
- 6. A qualified life has not been established for Barton transmitters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. I m
m r
Joseph M. Faney Nucl:ar Pl:nt Unit 1
SECTION C.2.4 Sheet 30 v.
ENVIR NMENT DOCUMENTATION REF.
EQUIPMENT DESCRIPTION OUAL.
OUTSTANDING PA H AM ET Ell SPEC.
QUAL.
SPEC.*
OUAL.
METif0D ITEMS SYSTEM: Feedwater Control OPERATING Trip-5 min.
frip-5 min.
PLANT ID NO. Q1C22LT486 TIME Post DBF. -
Post DBE -
1 I
Note 3 None 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER BARTON PR ESSU RE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
)64 RELATIVE IlUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Feedwater Control CllEMICAL Il B0 3 3 H B03 3
SPH AY
+FaOli 4Na0ll 4
1 Note 3 None 10%,-~ for < 5 min.
6 = 5 x 107 SPEC:+1257. for 5 min.-4 n ACCURACY:
1SMADIATION Rads Note 3 4
i Note 3 None DEMON: Note 3 6 = No w 5 SERVICE:
Stm. Gen. Water Level LOCATION: Containment El. 168' AGING Note 4 Note 6 Note 4 riote 6 Note 6 None o
R FLOOD LEVEL ELEV:
115' SUDMER-0 ADOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A
- DOCUMENTATION R LFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to 1120F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
! 2.. J.M. Farley FSAR Figure 6. 2-6 16 psia in 11.5 days.
- 3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
- 4. J.M. Faricy FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-Oln.
- 5. For 6, the component is considered qualified if the 6 dose of 2 x 108 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been escr.blished for Barton transmitters.
An engineering analysis using activ. tion energies and regression curves for the constituent materials will be performed to establish end of 11fe.
Rev. l
Joseph M. Faney Nuct:ar Plant Unit 1
SECTION C.2.4 Sheet 31 of ENVIRONMENT EOUIPMENT DESCRIPTION DOCUMENTATION REF.
OUAL OUTSTANDING M ETilOD' ITEMS PA R AMETEll SPEC.
OUAL.
SPEC.'
QUAL.
SYSTEM: Feedwater Control OPERATING Trip-5 min.
frip-5 min.
WE Post W -
Post M -
1 I
Note 3 None PL ANT ID NO.
9IC22LT494 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PRESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MOOEL NUMBER:
764 RELATIVE ilUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Feedwater Control CilEMICAL Il B0 3 3 II B03 3
SPRAY
+Na0il
+Na0li 4
1 Note 3 None
+10%,-= for < 5 min.
N = 5 x 107 ACCURACY: SPEC: 25% for 5 min.-4 n DEMON: Note 3 osRADIATION Rads Note 3 4
1 Note 3 None 11 = Note 5 SERVICE:
Stm. Gen. Water Level LOCATION: Containment El. 168, AGING Note 4 Note 6 Note 4 Note 6 Note 6 None FLOOD LEVEL ELEV:
115' SunMER.
A00VE FLOOD LEVEL:
Yes GliNCE N/A N/A N/A N/A N/A N/A d
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 256oF in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to ll20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pre:-'_are profile f rom Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J.M. Farley FSAR Fir"- ' T. 2-6 16 psia in 11.5 days.
D. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference 1 for details.
- b. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B.
- 5. For 8, the component is considered qualifled if the 6 dose of 2 x 108 Rads is reduced by shiciding to 10% of the 6 alose.
- 6. A qualified life has not been established for Barton transmitters.
An engineering, analysis using activation energies and res;ression curves for the constituent materials will~be pe c cmed to establish end of life.
Rev. I
Joseph M. Farcy Nuclear Ptnt Unit i
SECTION C.2.4 Sheet 32 of ENVIR NMENT DOCUMENTATION REF.
QUAL ~
OUTSTANDING EOUIPMENT DESCRIPTION PARAMETE R SPEC.
OUA L.
SPEC.*
OUAL.
METHOD ITEMS SYSTEM: Feedwater Control OPE R ATING Trip-5 min.
trip-5 min.
Post DBE -
1 1
Note 3 None PLANT ID NO. QlC22LT495 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUF ACTURE R: BARTON PRESSURE 62.2 (PSIAl Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
764 RELATIVE ilUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Feedwater Control CilEMICAL II B0 R B03 3 3 3
SPRAY
+Na0li 4Na0ll 4
1 Note 3 None
+10%,-= z or < 5 min.
6=5x 107 ACCURACY: SPEC: 25% for 5 min.-4 nosUANANN NIS Note 3 4
1 Note 3 None DEMON: Note 3 6 = Note 5 SERVICE: Stm. Gen. Water Level El. 168' AGING Note 4 Note 6 Note 4 Note 6 Note 6 None 3
o LOCATION: Containment FLOOD LEVEL ELEV:
115' SUDMER.
A00VE FLOOD LEVEL: Yes GENCE N/A N/A N/A N/A N/A N/A
'DOCUMENTATIG'J
REFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 ti Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ra'np down to ll 20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I br.-45 min., ramp down to
- v. J.M. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
- c. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Referer.cc 1 for details.
. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B.
- 5. For 8, the component is considered qualified if the B dose of 2 x 108 Rads is reduced by shielding to 10% of the 6 dose.
- 5. A qualified life has not been established for Barton trmamitters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. I
~
.loseph M. Faney Nucl:ar PI:nt Unit 1
SECTION C.2'.4 Sheet 33 cf ENVIRONMENT DOCUMENTATION REF.
OUAL OUTSTANDING EOUlPMENT DE:./11PTION
. METHOi)
ITEMS P RAMETER SPEC.
QUAL SPEC.*
OUAL S'.' STEM: Feedwater Control OPERATING Trip-5 min.
Trip-5 min.
TwE Nst w.-
Ns t N. -
1 1
h3 None PLANT D NO.
QlC22LT496-4 months 4 months COMPONENT:
Level Transmitter TEMP.
300 l'F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PRESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
764 RELATIVE IIUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Feedwater Control CHErilCAL II B0 3 3 II B03 3
SPRAY 4 NaCll 4NaCll 4
1 Note 3 None
+10%,-= for < 5 min.
6 = 5 x 107 ACCURACY: SPEC: 25% for 5 min.-4 rros h ADI ATION Rads Note 3 4
1 Note 3 None DEMON: Note 3 8 = Note 5 SERVICE:
Stm. Gen. Water Level LOCATION: Containment El. 1 (2 8 '
AGING Note 4 Note 6 Note 4 Note 6 Note 6 None FLOOD LEVEL ELEV:
1IS' SUDMER-0 A00VE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
' dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to ll20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J.M. Parley FSAR Figure 6. 2-6 16 psia in 11.5 days.
- 3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference i for details.
- 4. J.M. Paricy FSAR Tabic 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-Oln.
- 5. For 8, the component is considered qualified if the 6 dose of 2 x 108 Rads is reduced by snielding to 10% of the 8 dose.
- 6. A qualified life has not bec.n established for Harton transmitters.
An engineering analysis using activation energies and regression curves for the constituent materials will ne performed to establish end of life.
Rev. 1
Joseph M. l'arley Nuct:ar Pirnt Unit 1
SECTION C.2.13 Sheet 53 ef ENVIR0NMENT DOCt2NIENTATION REF.
EQUIPMENT DESCRIPTION OUAL-OUTSTANDING PA RAME TE R SPEC.
QUAL.
SPEC.
QUAL.
METHOD ITEMS SYSTEM: Main Steam OPERATING Trip-5 min.
Trip-5 min.
PLANT ID NO.
Q1N11LT477
]
TIME Post DBE -
Post DBE -
I I
Note 3 None 4 months 4 months COMPONENT:
Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PR ESSU RE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 None MODEL NUMBER:
764 RELATIVE ilUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Level Control CHEMICAL ll B0 II BG3 3 3 3
SPRAY 4 NaOli
+NaOli 4
1 Note 3 None 6 = 5 x 107 ACCURACY: SPEC:
25%
RAnlA ON Rads DEMON: Note 3 Note 'l 4
I Note 3 None 6 = Note 5 SERVICE:
Stm. Gen. Water Level LOCATION: Containment El. 116 AGING Note 4 Note 6 Note 4 Note 6 Note 6 None R
FLOOD LEVEL ELEV:
115' SUBMER.
2 ADOVE FLOOD LEVEL:
Yes GENCE N/A N/A N/A N/A N/A N/A c DOCUMENTATION
REFERENCES:
NOTES:
. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to ll20F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
, J.M. Parley FSAR Figure 6.2-6 16 psi in 11.5 days.
> J.M.
Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Referente I for details.
> J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE nulletin 79-01B.
- 5. For S, the componens is considered qualified if the 6 dose of 2 x 108 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been established for Barton transmitters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. 1
Joseph M. F..cy Nuclear Plant Unit 1
SECTION C.2.13 Sheet 54 of ENVIHdNMENT DOCUMENTATION REF.
QUAL-OUTSTANDING EQUIPMENT DESCRIPTION Pall A MET Ell SPEC.
OUAL.
SPEC.*
OUAL.
METHOD ITEMS SYSTEM: Main Steam OPERATING Trip-5 min.
Trip-5 min.
TIME Post DDE -
Post DBE -
1 1
Note 3 None PLANT ID NO.
Q1NllLT487 '
4 months 4 months COMPONENT: Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PRESSU RE 62.2 (PSIA)
Note 2 Note 3 3
i Note 3 None MODEL NUMBER:
764 RELATIVE I!UMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Level Control CllEMICAL Il B0 3 3 II B03 3
SPRAY
+Na0li
-l Naoli 4
1 Note 3 None ACCURACY: SPEC: +25%
6 = 5 x 107 RADIATION Rads Note 3 4
1 Note 3 None DEMON: Note 3 H = Note 5 SERVICE:
Stm. Gen. Water Level AGING 2
LOCATION: Containment El. 116, Note 4 Note 6 Note 4 Note 6 Note 6 None k
FLOOD LEVEL ELEV:
115' SUBME R-ABOVE FLOOD LEVEL: Yes GENCE N/A N/A N/A N/A N/A N/A
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature r afile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F le*ter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to 1120F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwell at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J.M. Farley FSAR Figure 6.2-6 16 psia in 11.5 days.
- 3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference a fo-details.
- 4. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-Oln.
- 5. For 6, the component is considered qualified if the 6 dose of 2 x 108 Rads is reduced by shielding to 107. of the 6 dose.
- 6. A qualified life has not been established for Barton transmit ters.
An engineering analysis using activation energies and regression curves for the constituent materials will be performed to establish end of 1ffe.
Rev. I
Joseph M. Faney Nucl= r PI:nt Unit i
SECTION C.2.13 Shret 55 of ENVlil NMENT DOCUMENTATION REF.
QUAL
QUAL.
SPEC.*
OUAL.
METHOD ITEMS SYSTEM: Main Steam OPERATING Trip-5 min.
trip-5 min.
PLANT ID NO.
Q1N11LT497 TIME Post DBE -
Post DBE -
1 I
Note 3 None 4 months 4 months COMPONENT: Level Transmitter TEMP.
300
("F)
Note 1 Note 3 2
1 Note 3 None MANUFACTURER: BARTON PR ESSURE 62.2 (PSIA)
Note 2 Note 3 3
1 Note 3 t'one MODEL NUMBER:
764 IIE LATIVE ilUMIDITY (%)
100 Note 3 4
1 Note 3 None FUNCTION:
Level Control CHEMICAL 13 B0 3 3 II B03 3
' PRAY 4Na0ll
+Na0ll 4
1 Note 3 None ACCURACY: SPEC:
25%
6 = 5 x 107 HADIATION Rads Note 3 4
I Note 3 None DEMON: Note 3 6 = Note 5 SERVICE:
Stm. Gen. Water Level AGING E
LOCATION: Containment El. 116' Note 4 Note 6 Note 4 Note 6 Note 6 None
!2 FLOOD LEVEL ELEV:
115' SUBMER-0 ABOVE FLOOD LEVEL: Yes GENCE N/A N/A N/A N/A N/A N/A p
I o
- DOCUMENTATION
REFERENCES:
_ NDTES:
- 1. Westinghouse letter APW-A-5141
- 1. Temperature profile from Reference 2.
Ramp up to 300 F from ambient in 50 sec.,
dated 2-14-80 & Westinghouse ramp down to 2560F in 16 min., ramp down to 1800F in I hr.-7 min., dwell at 1800F letter NS-TMA-2184, Anderson to f r 6 hrs.-56 min., and ramp down to 1120F in 11.5 days.
Stoltz (Test) (Westinghouse
- 2. Pressure profile from Reference 3.
Ramp up to 62.2 psia in 40 sec., dwe.1 at Proprietary Class 2) 62.2 psia for 6 min., ramp down to 26.7 psia in I hr.-45 min., ramp down to
- 2. J.M. Farley FSAR Figure 6. 2-6 16 psia in 11.5 days.
- 3. J.M. Farley FSAR Figure 6.2-4
- 3. Westinghouse Proprietary information.
See Reference I for details.
- 4. J.M. Farley FSAR Table 3.11-1
- 4. Enclosure (4) to IE Bulletin 79-01B,
- 5. For S, the component is considered qualified if the 6 dose of 2 x 108 Rads is reduced by shielding to 10% of the 6 dose.
- 6. A qualified life has not been established for Barton transmitters.
An engineering analysis ueing activation energies and regression curves for the constituent materials will be performed to establish end of life.
Rev. I 1
.