ML20076K383
| ML20076K383 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/06/1983 |
| From: | Drummond F LOUISIANA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8307080442 | |
| Download: ML20076K383 (47) | |
Text
I
~
o LOUISIANA P O W E R & L I G H T! P O BOX 6008
- NEW ORLEANS LOUlE ANA 70174 442 OuAnONoe sineer
- (504) 366-2345 mwstac July 6, 1983 W3183-0177 3-A1.01.04 3-A19.09.10 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 Implementation of Regulatory Guide 1.97 Rev 2.
REFERENCE:
LP&L letter W3P83-1194 Gentlemen:
The above referenced letter provided LP&L's proposed schedule for completing the requirements of NUREG 0737 Supplement 1.
In keeping with this schedule please find attached our report describing the implementation of Regulatory Cuide 1.97 Rev. 2 at Waterford 3.
If you have any questions please feel free to contact me or R. W. Prados.
Yours very truly i
. J. Drummond bA Project Support Manager FJD/ DEB /cmk Enclosure cc:
W. M. Stevenson, E. L. Blake, J. Wilson, J. Shea 8307080442 830706 PDR ADOCK 05000392 I(
F PDR
)
4
RESPONSE
TO REGULATORY GUIDE 1.97 REV 2 l
1 June 1983 1
I I
s LOUISIANA POWER & LIGHT COMPAYY WATERFORD SES UNIT No. 3 RESPONSE TO REGULATORY CUIDE 1.97 REV. 2 Table of ContentsSection I
Introduction II Regulatory Guide 1.97 Revisica 2 Criteria III Evaluation Criteria IV Evaluation Lethod V
Type A Variables VI Summary Table 1 Waterford-3 Design and Qualification Guidelines of Regulatory Guide 1.97 Rev 2 PAMI Table 2 Response to Regulatory Guide 1.97 Revision 2 Table 3 Waterford-3 Exceptions to Regulatory Guide 1.97 Revision 2 Recommendations Table 4 Waterford-3 Post-Accident Monitoring Instrumentation to be Provided After Fuel Load.
i i
i I
l - - _.
__. _ _ _. _ _. ~.
I.
INTRODUCTION The objective of this report is to provide the Nuclear Regulatory Commission with a detailed account of the conformance of Louisiana Power & Light Company's Waterford SES Unit No. 3 to the recommendations of Revision 2 to Regulatory Guide 1.97 (Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs During and Following An Accident). The information provided herein meets the requirements of Supplement 1 to NUREG-0737 (Requirements for Emergency Response Capability), Section 6.
Sections II through VI of this report discuss the requirements of the guide, the evaluation criteria, and the evaluation methods of this report. Table 1 summartz.is the evaluation criteria and Table 2 provides a line by line comparison of Waterford-3 to the requirements of the guide.
In most cases, Waterford-3 will meet the intent of the guide by fuel load. Table 3 itemizes justifiable deviations from the guide. Table 4 lists instrumentation that will be installed after fuel load.
Should NRC re-evaluation of Regulatory Guide 1.97 variables result in any relaxation of the requirements, LP&L may elect to appropriately 1.
modify certain aspects of the program as described herein.
i l 4
II.
REGULATORY CUIDE 1.97, REVISION 2 CRITERIA The guide groups Post-Accident Monitoring Instrumentation into five functional types (Types A, B, C, D and E), and into three categories of design and qualificattun requirements (Categories 1, 2 and 3).
The category assigned to an instrument of a specific functional type depends on its importance i.e., whether it is the key variable for achieving a specific monitoring function, or is a back-up or indication to verify the correctness of the key variable.
The f unctional types are defined below:
- Type A - Those variables to be monitored that provide the primary information required to permit the Control Room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events. Primary information is information that is essential for the direct accomplishment of the specified safety functions: it does not include those variables that are associated with contingency actions that may also be identified in written procedures.
l Type B - Those variables that provide information to indicate whether plant safety functions are being accomplished. Plant safety functions are (1) reactivity control, (2) core cooling, (3)
~
maintaining reactor coolant system integrity, and (4) maintaining containment integrity (including radioactive effluent control).
Variables are listed with designated ranges and categories for design and qualification guidelines. Key variables are indicated i
by design and qualification Category 1.
- Type C - Those variables that provide information to indicate the potential for breaching or the actual breach of the barriers to fission product releases. The barriers are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment.
- Type D - Those variables that provide information to indicate the operation of individual safety systems and other systems important to safety. These variables are to help the operator rake to appropriate decisions in using the individual systems important safety in mitigating the consequences of an accident.
- Type E - Those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases, i
Category 1 provides the most stringent requirements and is intended for key variables. Category 2 provides less stringent requirements and generally applies to instrumentation intended for indicating system operating status. Category 3 is intended to provide requirements that will ensure high quality off-the-shelf instrumentation is obtained and applies to backup and diagnostic instrumentation. It is also used where the state-of-the-art will not support requirements for higher qualified instrumentation.
Category 1 requires Class 1E, seismic and environmental qualification and applies to all key variables. All Type A and some Type B, C, D and E variables are Category 1.
Category 1 equipment is always safety-related and requires Class IE power supply, channel independence and direct indication or recording on at least one channel.
Category 2 instrumentation requires environmental qualification.
Seismic qualification, however, is only imposed if it is part of n safety-related system. The power supplies need not be Class 1E but should be from a highly reliable source. Its display may be via a dedicated instrument or it may be processed for display on demand by CRT or other means. Category 2 generally applies to key Type D and E variables..
Category 3 calls for high quality industrial off-the-shelf instrumentation and generally applies to backup variables for Types B, C, D and E.
III.
EVALUATION CRITERIA In many cases a variable may be listed under more than one functional type heading. For example, Core Exit Temperature is listed under Type B variables as a Category 1, and under Type C as a Category 3 instrument. In other cases, a variable may be listed more than once under the same type heading. For example, RCS Cold Leg Water Temperature, is listed under Type B as a Category 3 ins trumen t for Reactivity Control Verification and as a key variable with consequent Category I requirements for detection of Core Cooling.
In the above instances, conformance to the regulatory guide is based on the more stringent categorization.
The specific criterie which were used for the evaluation of Waterford-3 against Regulatory Cuide 1.97 Revision 2 are summarized in Table 1 of this report and are discussed further below.
Environmental Qualification In response to NUREG-0588 (Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment), LP&L submitted to the NRC in December 1981 a document entitled " Response, _. _ _ _ _
l to NUREG-0588" (Revision 2 to this document was submitted in November 1982).
It presents the results of an in-depth program to review and document the environmental qualification of equipment located in a harsh environment which is required to mitigate or monitor an accident and/or place the plant in a cold shutdown condition.
It identified all equipment not yet qualified. Such equipment will eithar be qualified for interim operation, relocated to a less demanding environment, or replaced.
All Regulatory Guide 1.97 Revision 2 Category 1 and Category 2 Post Accident Monitoring Instrumentation located in a harsh environment have been evaluated and will be ultimately qualified within the scope of this report.
It will therefore be subject to the NRC's Environmental Qualification Audit. The details of the qualification status of all equipment, including post-accident monitoring instrumentation, is contained in the submittal mentioned above. The NRC will be informed of the qualification progress and status of this equipment prior to fuel load. As with all equipment within the purview of the Environmental Qualification program, interim justifiestion for operation will be provided for all Regulatory Guide 1.97 Post-Accident Monitoring Instrumentation not qualified by fuel load. _,
All Category 1 and 2 equipment located in a mild environment as a minimum meets the environmental qualification criteria of IEEE-323-1971.
Seismic Qualification The Waterford-3 basic criteria for seismic qualification of electrical equipment and instrumentation is contained in FSAR Section 3.10.
In general original equipment was qualified with ~
IEEE-344-1971, although in some cases, it was qualified to IEEE-344-1975.
Instrumentation being added as a result of the Regulatory Guide 1.97 Rev 2 guidelines for Category 1 equipment has s
been qualified to IEEE-344-1975.
Category 2 equipment that is part of the pressure boundary for safety-related systems or performs a safety-related function other than its Regulatory Guide 1.97 Rev 2 function is qualified in a similar manner to that of Category 1 equipment.
From August 31 to September 3,1982, the NRC and their consultants from EG&G conducted a Seismic Qualification Review Team (SQRT) audit A.
Y e
7-
- _ _ _ _ = _ _ _.
)
at the Waterford-3 site. This consisted of a comparison of the actual installation of selected components versus the installation drawings and the seismic qualification test or analysis configuration. A review of the seismic test reports was then conducted. Formal documentation of this audit is expected in a future SER Supplement.
Power Supply Unless justification is provided, Regulatory Guide 1.97 Revision 2 instrumentation power supplies are as discussed below:
Category 1 instrumentation is powered from one of the following:
- 2) Class IE 120V AC Emergency - Backed by an Emergency Diesel Generator
- 3) Class IE 125V DC Category 2 instrumentation is powered, as a minimum from one of the following highly reliable sources:
l r..,._.. _ _.
- 1) Non-safety 120V Vital AC (Uninterruptible)
- 2) Non-saf ety 120V AC In many instances, Category 2 instrumentation is powered from the safety-related sources.
A detailed discussion of these systems can be found in FSAR Section 8.3.
IV.
EVALUATION METHOD Table 1 of this report (Design and Qualification Requirements of Regulatory Guide 1.97 Revision 2) presents a summary of the qualification criterion imposed on Waterford SES Unit No. 3 Post-Accident Monitoring Instrumentation.
Table 2 (Response to Regulatory Guide 1.97 Revision 2) provides a line-by-line comparison of Waterford SES Unit No. 3 to the requirements of Table 2 of the guide.
In certain cases the instrumentation listed in this table will not be available by fuel load. Such instrumentation is itemized in Table 4 Columns 1 through 4 list the type, category ee t arfsble as stipulated in the
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1 Guide. A reference number is provided in column 2 so that each variable may be referred to by an alpha-numeric combination of its type plus reference number (e.g., Neutron Flux is B-1).
Columns 5 through 11 provide the actual design and qualification information on the instruments used at Waterford-3 in accordance with Supplement 1 to NUREG-0737.
Table 3 lists deviations from the recommendations of the guide. They all involve exceptions to the ranges specified by the guide and are either considered insignificant or due to plant specific features.
In certain cases the instrumentation listed in Table 2 will not be available by fuel load. Such instrumentation is itemized in Table 4 A subset of variables listed in Table 2 of this report and Table 2 of the guide have been determined to meet the definition of Type A variables. These are discussed in Section V below.
V.
TYPE A VARIABLES Regulatory Guide 1.97 Rev 2 defines Type A variables as follows:
"Those variables to be monitored that provide the primary information - --
required to permit the Control Room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis events. Primary information is information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures."
Type A instruments are therefore those that an operator must refer to before performing some specific, planned, manual action during his response to a design event.
Definition of Design Basis Event The definition of a design basis event, in the context of Regulatory Guide 1.97 Rev 2, is that used in the ANS 4.5 (Standard on Accident Monitoring Instrumentation) which formed the basis for the Regulatory Guide.
It defines Design Basis Events as:
1.
Those events postulated in the plant safety analyses, any one of which may occur during the lifetime of a particular plant, excluding those events which are expected to occur during a calendar year for a particular plant. _
- 2. Those events that are not expected to occur but are postulated in the plant safety analyses because their consequences would include the potential for the release of significant amounts of radioactive material.
For Waterford-3, therefore, these events equate to those defined in FSAR Chapter 15 as Infrequent Incidents or Limiting Faults. However, since it is specifically called out in the Reg Guide (p 1.97-2), the ATWS event has also been included. Moderate Frequency Incidents (also known as Anticipated Operational Occurrences), which are expected to occur once per year, such as turbine trip, and loss of offsite power, are excluded.
Type A variables, therefore, were determined by reviewing each Emergency Operating Procedure related to an FSAR Chapter 15 Infrequent Incident and Limiting Fault, and the ATWS procedure.
Accordingly, the following Emergency Operating Procedures were reviewed for identification of Type A variables:
LO CA Loss of Reactor Coolant Forced Flow Excess Steam Demand Loss of AC Power Loss of Main Feedwater SG Tube Rupture _ _,
Anticipated Transient Without Scram Inadequate Core Cooling As a result of this review the following parameters have been identified as Type A:
1.
RCS Pressure 2.
RCS Hot Leg Temperature 3.
RCS Cold Leg Temperature 4.
Containment Pressure 5.
Containment Rydrogen Concentration A discussion of each of the above parameters which are also part of Table 2 follows:
RCS Pressure /
RCS Hot Leg Temperature /
RCS Cold Leg Temperature These three variables are used as inputs for calculating margin to subcooling.
If RCS temperature exceeds the saturation temperature corresponding to RCS pressure, the procedures require that the Reactor Coolant Pumps be stopped manually. _.___ __
4 As indicated in Table 2, the instrumentation for RCS Pressure (B7, B11, C4, C9) the RCS Hot Leg Temperature (B6), and RCS Cold Leg Temperature (BS), meet the requirements of Category 1.
Containment Pressure During a LOCA, in the absence of a Recirculation Actuation Signal, the Containment Spray Pumps must be manually stopped to avoid reaching minimal containment design pressure.
As indicated in Table 2, the instrumentation for Containment Pressures (A5) meets the requirements of Category I.
Containment Hydrogen Concentration This is the primary variable the operator will use in order to decide when to manually place the hydrogen recombiners into operation. As indicated in Table 2, this variable (C10) meets Category I requirements.
VI.
SUMMARY
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This report demonstrates that Waterford-3 will meet the intent of Regulatory Guide 1.97 Revision 2.
A considerable number of design changes have been made since issuance of Regulatory Guide 1.97 and _..,,
VI.
SUMMARY
(Cont'd)
NUREG-0737 to facilitate conformance with the recommendations and requirements of these' documents.
This report should be considered as a response to the documentation requirements of Supplement 1 to NUREG-0737 (Section 6.2).
Many of the variables listed in Table 2 will also be available on the Waterford-3 Safety Parameter Display System (SPDS), which will have displays in both the Technical Support Center (TSC) and the Emergency Operations Facility (EOF).
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TABLE 1 WATERFORD-3 DESIGN AND QUALIFICATION GUIDELINES OF REGULATORY GUIDE 1.97 REV 2 PAMI CRITERION CATEGORY 1 CATEGORY 2 CATEGORY 3 Environmental Yes Yes No Qualification (NUREG-0588)
Seismic Qualification Yes If part of a No (in accordance with safety-related the Criteria of FSAR system Section 3.10)
Yes( }
No No Single Failure Criterion Physical Independence Yes Yes No (Reg Guide 1.75)
No( >
Direct Indicating Yes; on at No or Recording Device least one channel _
TABLE 1 (Cont'd)
CRITERION CATEGORY l CATEGORY 2 CATEGORY 3 Energized from Yes No( )
No Emergency Diesel Generator QA 10CFR50 Applicable No Appendix B Portions of 10CFR50 Appendix B NOTES:
(1)
One channel for each redundant division except 4 channels for Steam Generator level.
(2)
The method of display may be by dial, digital, CRT or strip chart recorder. Effluent radioactivity monitors, area radiation monitors, and meteorology monitors should be recorded.
(3)
Should be highly reliable, not necessarily energized f rom the Emergency Diesel Generator. The non-Class 1E Vital (Uninterruptible) supply is acceptable. - - _ - _
i Sheet 1 of 25 TABLE 2 NOTES LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT No. 3 RES PONSE TO REGULATORY CUIDE 1.97 REVISION 2 NOTE (1) - Environmental Qualification The following notations are used in the column 8a to explain environmental qualification status:
A - Either all or part of the components of this instrumentation loop fall within the scope of the LP&L report entitled " Response to NUREG-0588". Any parts.of this loop not located in a harsh environment and therefore not within this report's secpe are qualified for the mild environment in which they are located.
B - This instrumentation loop is Class 1E, is located in a mild environment, is qualified to function in such an environment and, as a minimum meets the criteria IEEE-323-1971.
C - This instrumentation is non-Class lE and is qualified to withstand its specified service environment.
NOTE (2) - Seismic Qualification The following notation is used in the column 8b to explain seismic qualification status:
A - Qualified in accordance with the criteria of FSAR Section 3.10.
NOTE (3) - Quality Assurance The following notation in the column 9 is used to explain the level of quality assurance applied:
A - This instrument is designated Class lE.
This designation includes all sensing line, instrument valves and ins trument racks. As such it is subject to the quality assurance program in accordance with 10CFR50 Appendix 3.
O SHEET 2 OF 25 TABLE 2 IAUISTANA F0WER & LICHT COMPANY WATERFORD SES UNIT NO. 3
RESPONSE
TO RECUIATORY CUIDE 1.97 REVISION 2 1
2 3
4 5
6 7a 7b sa sb 9
10 31 1.OCATION/ TAC NO.
QUALIFICATION NO.
INSTRUIENT ENVIROM-QUALITY OF RA TE NENTAI.
SEISNIC ASSURANCE POWER TYIE NO.
CAT.
VARIABLE CHAN.
11t 0VIDED SENSOR DISPtAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLT NOTES REF.
l j
Reactivity
^
Control i
B 1
1 Neutron Flux 4
10~8-200%
in Containment CR RTCB Pane!
A A
A Class IE CP7 Indicators Vital B
2 3
Control Rod Inse rt ion in Containment CR RTCB Panel A
A A
Non-Position Position CP2 Position CRT Class IE Pull Travel Vital Indicator Module 11ropped Rod M A Nimic Display A
A A
Non-Class IE Indication Module Vital B
3 3
RCS Soluble 10-5000 pra RAB Relay Re. Borono-B NA NA Non-Required in'strument meter Panel Class 1E range is 0-6000 ppm Boron Con-provided range of LCP65 Indicator centration 10-5000 pra is plant specific. The analy-ses indicate that the concentration will not exceed 2300 ppe.
h
SHF.ET 3 0F 25 1
2 3
4 5
6 7a 7b Ba 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUDENT OF RANCE MENTAL SEISNIC ASSURANCE POWER TY PE No.
CAT.
VARI ABLE CitA N.
PROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2) NOTE (3)
SUPPLT NOTES REF.
Core Cooling 8
4 3
RCS Cold 1
in Containment CR RTCS Indicators A
A A
Class IE Vital B
6 I
lag Water Per 50-750*F Panel CP8 &
Temp.
Cold LCP-43 k8 18, 2A 1 Per in Containment QSPDS Plasma A
A A
Class IE Vital Cold 50-750*F Display Panel CP6 Les 1A, 18, j
2A, 28 Ditto 0-600*F Recorders A
A A
Class IE Channe! chosen by Vital selector switch for CR RTCB Panel CP2 IA or 15, 2A
[
or 25 i
B 5
I RCS Hot lag 1
50*F-7 50*F In Containment CR RTCB Panel A
A A
Class IE Range indicated to be i
Vital provided by coussercial CP8 Indicators l
Water Temp.
Per
& LCP-43 operation. Instrumen-Hot tation available at lag Puel Load as indicated j
162 in Table 4.
Ditto 525'F-675*F Recorders A
A A
Class IE Vital CR RTCB Panel CP2 1 Per 50 *F-7 50 *F In Containment QSPDS Plasma A
A A
Class IE Vital H. I.. )
Display Panel 2 Per CP6 H.L 2 Refer to Variable 8
6 1
RCS Cold Leg B4 Water Temp.
M I
1
SHEET 4 OF 25 I
2 3
4 5
6 7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION NO.
INSTRUNENT ENVIRON-QUALITT REF.
OF RANCE NENTAL SEISNIC ASSURANCE POWER TYPE NO.
CAT.
VARI ABLE CHAN.
11tOVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Cote Cooling (Cont'd)
B 7
1 RCS Pressure 4
0-3000 psig in Containment CR RTCB Panel A
A A
Class IE Required Dange is Vital 0-4000 pets.
Pro-(CP7) Indicators a 11 1
vided Range is con-
& Recorder C
4 1
sidered adequate pend-C 9
1 1
ing the resolution of A1WS tesue.
B 8
3 Core Exit 2
200*F-2300*F In Containment CR RTCB Panet A
A A
Class IE Waterford-3 will be CR7 Recorders Vital implementing an In-C 1
1 Temperature adequate Core Cooling System designed by CE to meet the intent of NUREC-0737 Item II.F.2.
This system will provide indt-cations and alarms to alert the operator to an approach to in-Class IE adequate core cooling.
8 32*F-2300*F in Containment QSPDS Plasma Vital it will include inputs Per Display Panel from 56 Core Exit Channel 162 Chan.
Thermocouples, and from RCS Hot and Cold f.eg Temperatures and Pressurtzer Pressure.
B 9
1 Coolant Level 2
From Align-In Reactor CR RTCB Panel A
A A
Class IE The inputs will be in Reactor ment Plate to CP7 Recorders (2)
Vital processed to indicate subcooled margin and Upper Culde and QSPDS will provide indica-Support Plate tions of volding, 0-100% and This system is des-f rom Upper cribed in FSAR Cutde Support Section 1.9.30 and the Plate to Top CE 4acuments refer-of Reactor enced therein. Con-Dome 0-100%
firmatory operator B
10 2
Degrees of Sub-2 200*F Sub-In Containment CR RTCB Panet A
A A
Class IE procedures shall be cooling cooling to CP2 & CP8 Vital provided for sub-50*F Super-Indicators (4),
cooling variables, heat
,s&
SHEET 5 or 25 1
2 3
4 5
6 7s 7b 8a 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITT NO.
INSTRUIENT MENTAL SEISNIC ASSURANCE POWER TYPE NO.
CAT.
VAtlARLE CHAN.
59t0VIDED SENSOR DISPLAT IEJTE (1)
NOTE (2)
NOTE (3)
SUPPLT NOTES OF RANCE REF.
Core Cooling (Cont'd) 700*F Sub-QSPDS Plasma cooling to Display Panel 2100*F Super-CP6 heat 200*F Sub-CR RTC8 Panel CP7 cooling to Recorders (2) 200*F Super-Iwat Maintaining RCS Inte grit y l
Refer to Variable B
11 1
RCS Pressure 57 3
B 12 Containment C
6 Sump Water 1.e ve1 I
Wide Range 2
0-20 ft in Containment CR RTCB Panel A
A A
Class IE Vital CP8 Indicator (by Volume)
(742,000 Cal CP8 Recorder Equivalent)
& QSPDS Plasma Display Panet Channel 1 & 2 2
Marrow Range 2
0-30 ft in Containment CR RTC8 Panet A
A A
Class IE Vital CP8 Indicator (by volume)
(4000 Cat CPS Recorder Equivalent)
& QSPDS Plasma Display Panel Channel I & 2 h
e SHEET 6 or 25 I
2 3
4 5
6 7a 7b sa 8b 9
10 11 LOCATION QUALIFICATION NO.
INS 11tUMENT ENVILON-QUALITY REF.
OF RANGE MENTAL SEISMIC ASSURANCE POWER TY PE No.
CAT.
VARI ABLE CHAN.
PROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Maintaining Containment Integrity i
B 13 1
Containment 2
0-70 psia Instrum. Cabi-Ot RTCB Panet A
A A
Class IE Containment Design i
B 15 1
Pressure net In Con-CP8 Indicator Vital Pressure is 44 psig C
5 1
tainment CP8 Recorder S
Direct Indication pro-B 14 1
Containment vided for all automa-Isolation Valve tically operated Position valves. Non-automa-Valves inside NA Ope n-Closed Limit Switch CR RTC8 Ind.
A A
A Class IE tic valves are locked Cont a t nment In Containment Lts.
Vital closed. Post accident instrumentation Valves Outside NA Ope n-Closed Limit Switch CR RTCB Ind.
B A
A Class IE valve positions are Containment Outside Con-Las.
Vital monitored by computer.
tainment Fuel Cladding i
Refer to Variable C
1 1
Core Exit 88 Temperature C
2 1
Ra dioac t ivity NA NA NA C
NA NA Non-Provided by Crab Class IE Sampe Analysis of J
Concentration or Variable E-19 in Radiation Level Radiochen Lab.
in Circulating Refer to FSAR Sub-Primary Coolant section 9.3.8, " Post Accident Sampling System." A system which would meet Category I require-ments is not com-mercially available.
1 4
SHEET 7 0F 25
= -
I 2
3 4
5 6
7a 7b Ba 8b 9
10 II LOCATION QUALIFICATION NO.
INSTRUMENT ENVIRON-QUALITY REF.
OF RANCE NENTAL SEISMIC ASSURANCE POWER TYPE NO.
CAT.
VARIABLE CilAN.
11LOVIDED SENSOR DISrLAY NOTE (1)
NOTE (2)
NdTE (3)
SUPPLY NOTES Fuel Cladding (Cont'd)
C 3
3 As.alysis of 1
10 pC1/gm to NA NA C
NA NA Non-Neasurement provided Class IE by E19. See FSAR Sub-Primary Coolant 10 C1/gm section 9.3.8, " Post (Casuna Spectrum)
Accident Sampling System."
Reactor Coolant gesure Boundary Refer to Variable C
1 RCJ Pressure 37 Refer to Variable C
5 l
containment Bl3 Pressure Refer to Variable C
6 1
Containment B12 Sump Water Level Measurement provided C
7 3
Containment Area by El Radiatton Refer to Variable C
9 1
RCS Pressure B7 Measurement provided C
8 3
Effluent Radio-by E6 activity - Noble Cas Effluent from condenser Air Removal System Exhaust Containment C
10 1
Cont ainment 2
0-10%
Analyrer in CR Panel A
A A
Class IE Ilydrogen Con-RAB CP33 Recorders Emergency centratton
1 SHEET 8 0F 25 1
2 3
4 5
6 7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION NO.
INSTRUMENT ENVIRON-QUALITT REF.
OF RANCE MENTAL SEISMIC ASSURANCE POWER TY PE NO.
CAT.
VARIABLE CHAN.
PR OVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLT NOTES Cont ai nment (Cont'd)
C 11 1
Co nt ai nment 2
-5 t o RAB CR RTC8 Panet B
A A
Class IE Containment Design Pressure 195 psig CP8 Recorders Vltal Pressure is 44 psig Measurement Provided C
12 2
Containment by E7 Effluent Radi o-activity - Noble Cases f rom Iden-tified Release Points C
13 2
Radiation Ex-1 10-I R/hr
-Rec i rc. Pe ne-CR CP-52 Ind.
A A
A No n-Complies with Condi-Class tions in RC 1.97 postice Rate Per to tration Ares & QSPDS Plasma (instJe butid-Area 10 R/hr
-Personnel Air Display Panel IE Note 7.
4 Emer-Isolation devices ings or areas, Lock Area e.g., auxilia ry
-SIS Sump gency with local display are located at El. 46 shield butiding Penetr. Area in RAB at CR corridor.
annulus, f uel
-Refueling Por additional area handling build-Canal Area monitoring refer to ing, which are Variable E2.
in direc t con-tact with pri-mary contain-ment where penetrations and and hatches are located)
See E4, E5, E7 and C
14 2
Effluent Radio-E9.
activity - Noble Cases (f rom Buildings as Indicated in Cl3)
SHEET 9 OF 25 I
2 3
4 5
6 7a 7b Sa 8b 9
to 11 LOCATION QUALIFICATION NO.
INS 11tutelT ENVIRON-QUALITY REF.
OF RANCE NENTAL SEISNIC ASSURANCE POWER I
TYPE NO.
CAT.
VARIABLE CilAN.
FROVIDED SENSOR DISP!AY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Shutdown Cooling S.E.*ll*
D 1
2 SDCS Cooling 2
0-7000 3pm Instrum. Cab.
CR RTCB Panel A
A A
Class IE Refer to Variable Water Flow (0-280% of in RAB CP8 Indicators Vital D7 for System Flow.
Design Flow)
& QSPDS Plasma CW Design Flow is Display Panel 3000 spa Channel 1 i
D 2
2 SDCS Heat Ex-2 0-400'F RAB CR RTCB Panet A
A A
Class IE CP8 Indicators Vital change Outlet CP8 Recorder Temperature
& QSPDS Plasma Display Panel Channel 1 Safety injection System 4
D 3
2 Safety inject-1 0-10 0%
Inst. Cab. In CR RTCB Panel A
A A
Non-fon Tank Per Instrument Containment CP8 Indicators Class IE Vital
- Level Ta nk Scale (12 to 88% of l
tank volume)
- Pressure 1
0-700 pelg Inst. Cab In CR RTCB Panel A
A A
Non-Required Pressure Per Containment CP8 Indicators Class IE Instrument Range is Vital 0-750 pets. Provided Tank range is plant spect-fic and equal to 115%
of operating pressure of 610 peig. (Tank Design Pressure is 700 pstg).
-memes
SHEET 10 OF 25 1
2 3
4 5
6 7e 7b 82 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUNENT NENTAL SEISNIC ASSURANCE POWER TYPE NO.
CAT.
VARIABLE CHAN.
11t0VIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES OF RANCE REF.
Safety injection System (Cont'd)
D 4
2 Safety inject-1 Open-Closed Limit Switch CR RTCB Panel A
A A
Class IE Emer-in Containment CP8 Ind. Its.
ion Tank gency Isolation Valve Position D
5 2
A NA Non-For CVCS Ciarging Class IE Flow refer to CP4 Indicator Charging Flow (113% of max.
Vital Variable D 26.
De sign
& QSPDS Plasma Flow 132 gpe)
Display Panel D
6 2
Flow in IIPSI System:
- To Cold 1sg 1
A NA Mon-Class IE CP8 Indicators Per (0-105% of Vital Le g De si gn f low)
& QSPDS Channel 1
- To Hot Irg 1
A NA Mon-Design Flow is Class IE 190 gpa CP8 Indicators Per (0-260% of Vital Leg Design Flow)
D 7
2 Flow in LPSI 1
0-5500 gpm RAB CR RTCB Panet B
A A
Class IE Design Flow is Vital 4050 gre System Pe r (0-13 2% of CP8 Indicators tsg Design Flow)
D 8
2 Refueling Water 4
top to RA8 CR RTC8 Panel B
A A
Mon-Class lE CP7 Indicators Storage Pool Bottom.
Vital Level Instrument Scale 0-100%
exammmmme
4 SIIEET 11 OF 25 1
2 3
4 5
6 7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION NO.
INSTRUMENT ENVIRON-QUALITY REF.
OF RANCE MENTAL SEISMIC ASSURANCE POWER TYPE NO.
CAT.
VARIABLE CilA N.
PROVIDED SENSOR DISPIAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Primary Coolant System D
9 3
Peactor Coolant 1
0-1200 A BAB CR RTCB Panet B
A A
Mon-Pump Status CP2 Indicator Class IE D
10 1
Pressurizer 2
Cl osed-Not In Contain-CR RTCA Panet A
A A
Class IE Valve position is Per Safety Valves Closed ment CF2 Ind. Lights Vital detected by Acoustic Valve Pnsition
& QSPDS Plasma Monitoring System Display Panel sensors. Signal Pro-Channel I cessors are installed in Vibration and Loose Part Monitoring Panel CP32.
}
D 11 1
Pre ssurizer 2
0-100% in-In Containment CR RTCB Panel
.A A
A Class IE Level strument CF2 Indicators Vital Scale.
& Recorders (Lowest Con-nection to Iltghest Con-nection)
D 12 2
Pressurizer 1
0-300 A Switchg.ar CR RTCB CP2 C
NA NA Class IE Proportional Per Indicators Emer-11 eater Status lleater gency l
D 13 3
Quench Tank 1
Top to Inst. Cab. In CR RTCB Panel A
A A
Non-Level Bottom of Containment CF2 Indicator Class IE Tank Vital 0- 10 0%
i
.--mm
SHF.ET 12 OF 21 I
2 3
4 5
t>
7a 7h 8a 8b 9
10 11 LOCATION QUALIFICATION NO.
INSTRUIENT ENVIRON-REF.
OP RANGE tpALITY NENTAL SEISNIC ASSURANCE POWER TYPE NO.
CAT.
VARIABLE CHAN.
FROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Primary Coolant System (Cont'd)
D 14 3
Quench Tank 1
50-7 50*F In Containment CR RTCB Panet A
NA NA Mon-Temperature CF2 Indicator Class IE Vital D
15 3
Quench Tank 1
0-150 psig In Containment CR RTC8 Panet A
NA NA Mon-Pressure CP2 Indicator Class IE 4
Vital e
Secondary System i
(Steam Generator) i D
16 1
Steam Cenerator 4
O-100%
Inst. Cab. In CR RTCB Panet A
A A
Class IE le vel Per Instrument Containment CP8 Indicators Vital SG Scale.
& CP! Recorders (2)
(Rottom to Top Con-nection of Steam Cen.
4 D
17 2
Steam Cenerator 2
0-1300 pelg Inst. Ca b. I n CR RTCB Panet A
A A
Class IE Safety valve lowest Pressure Per (0-120% of Containment CP8 Indicators Vital SC Safety
& Recorders (2) setting is 1070 psig.
Valve Lowest Setting l
4
SHIET 13 0F 25 I
2 3
4 5
6 7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUPENT NENTAL SEISNIC ASSURANCE POWER OF RANCE TYPE NO.
CAT.
VARIABLE CHAN.
PROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES REF.
Secondary System (Steam Generator)
(Cont'd) 6 Instr. Cab.
OR STCB Panet A
A A
Non-D 18 2
Main Stese 2
0-8x10 Class IE Flow Indleatten Per ib/hr in Containment CPI Indicators Vital SC (106% of
& Recorders Nominal Flow)
D 19 3
Main Feedwater 2
NA NA Non-6 Class 1E Flow Ib/hr Instrum.
Indicators Vital (0-106% of Ca binet Recorders Design Flow) i Emergency Feed-I water System D
20 2
Emergency Feed-1 0-800 spe RAB CR RTC5 Panel B
A A
Class IE Vital water Flow (0-114% of instrum.
CP8 Indicators Design Flow) Ca binet D
21 1
Condensat e 2
0-25 f t RAB CR RTCB Pa ne t B
A A
Class IE Vital Storage Pool
( 0- 100%
instrum.
CF8 Indicators Water Level of scale)
Cabinet Containment Cooling Systems D
22 2
Cont ai nment 2
0-5000 gpm RAB CR RTCB Panet B
A A
Class IE Design Flow is Vits!
1750 gpa Spray Flow (0-280% of Instrum.
CP8 Indicators Design Flow) Cabinet i
m n
SilF.ET 14 OF 25 1
2 3
4 5
6 7a 7b Ra 8b 9
10 11 LOCATION QUALIFICATION NO.
INSTRUMENT EhvIRON-QUALITY REF.
OF RANCE MENTAL SEISMIC ASSURANCE POWER TYPE NO.
CAT.
VARI ABLE CHAN.
PROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Cantainment toolleg Systems (Cont'd)
D 23 2
Component Cool-2 0-1500 gpa RAB CR RTCB Panel B
A A
Class IE Emergency Design ing Water Flow Per (110% of Instrum.
CP18 Indicators Vital Flow is 1350 gpm to Containment Cooler Emerg.
Ca bi ne t Fan Coolers Design Flow)
D 24 2
Cont ainment 4
0*F-450*F RAB Coolers CR RTCB Panel B
A A
Class IE Atmosphere CP18 Recorders Vital Temperature (Containment Fan Coolers Inlet /
Outlet Temperature)
D 25 2
Containment 2
32*F-240*F RAB CR RTCB Panel A
A A
Class !E Required Range is Sump Water CP8 Indicator Vital 50-250*F Provided Recorder Range is Plant Temperature Specific.
Chemical and Vohree Control System D
26 2
CVCS Charging 1
A NA Non-Max. Design Flow is Flow (0-110% of Instrum.
CP4 Indicator Class IE IU gpe. Compare Design Flow) Ca bine t Vital Tariable D5 " Boric Acid Charging Flow".
D 27 2
Intdown Flow-1 0-150 gpa RAB CR RTCB Panel B
A NA Non-CVCS Letdown Out (0-Il71 of Instrum.
Ct'4 Indicatnr Class IE Design Flow is liesign Flow) Cabinet Vital 128 gpe.
uw
SHEET 15 0F 25 I
2 3
4 5
6 7a 7b 8a 8b 9
10 11 1.OCATION QUALIFICATION No.
INSTRUMENT EN%1RON-QUALITY REF.
OF RANCE MENTAL SEISMIC ASSURANCE POWER TYPE NO.
CAT.
VARIABLE CHAN.
lit 0VIDED SENSOR DISPIAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Chemical and Volume Control System (Cont'd)
D 28 2
Volume Control 1
A NA Non-Tank Level Bot tom of CP4 Indicator Class IE Tank (In-71tal dicator 0- 10 0%)
Cooling Water System D
29 2
Component 1
3 2-13 0*F RAB CR RTCB Panet B
A A
Class IE Required Range tg Cooling Water Per CP8 Indicators Vital 32-200*F.
Provided Temperature to Header Range 32-130*F is ESF System substantiated in (Component FSAR. Refer to Cooling Water Table 9.2-9.
(CCW Heat Exch.
Heat Exch. Tube Tube Side Out-Side Outlet Temp.
let Temp.)
120*F)
D 30 2
Component Cool-1
&-10000 gpm RAB CR RTCB Panet A
A A
Class IE CCW to ESF System ing Water Flow Per (0-14 7% of Instrum.
CP8 ludicators Vital Design Flow is to ESF System Header Design Flow) Cabinet 6800 gpm.
Radwast e Systems D
31 3
Hi gh-Isvel 1
Top t o RAB RAB CP4 8
A NA Non-Radioac t ive Per Bot tom of I nd ica t ot s Class IE Liquid Hold Up Tank Ta nk Vital Tank Level
( 0- 10 0%
Instrum.
Scale) w
SHEET 16 OF 25 I
2 3
4 5
6 7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUNENT NENTAL SEISNIC ASSURANCE POWER OF RANCE TYI1!
NO.
CAT.
V ARI AIILE CHAT;.
PROVIDED SENSOR DISPl.AY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES REF.
Radwaste Systems (Cont'd)
D 32 3
Radioactive Cas 1
& 600 psig RAB CR RTCB Panel B
A NA Non-Class IE CP4 Indicators Decay Tank Per (0-158% of Vital Pressure Tank Design Pressure)
Ventflatton System D
33 2
Emergency Ven-2 Open-Closed RAB CR RTCB Panet B
A A
Class IE All emergency vent!-
Vital or lation dampers which CP18 Ind. Lts.
tilation Damper Faer-change position on Position gency ESFAS.
Power Supplies D 34 2
Status of Stand-by Power and Other Energy Sources import-ant to Safety (llydraulic, Pneumatic)
Battery A, B, 1
A A
Class IE Vital CPI AB Voltage Per Batt.
SHEET 17 0F 25 I
2 3
4 5
6 7a 7b Sa 8b 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUMENT HENTAL SEISMIC ASSURANCE POWER RF.F.
OF RANCE TYPE NO.
CAT.
VARIABLE CHAN.
Mt0VIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Power Supplies (Cont'd)
Class IE Ba t tery A, B, 3
Annuncistor Battery Panel CR RTCB Vital AB Trouble Alors tc 1 and 2 2
0-5250 VAC DC l'anel CR RTCB B
A A
Class IE Emer-Voltage gency 14 1 and 2 Loa d 1
A A
Class IE Emer-Current Per CPI gency DC DC 1 and 2 2
55 to 65 Hz DC Panel CR RTCB B
A A
Class IE Emer-F requenc y gency DC 1 and 2 2
A A
Class IF.
Emer-VARS ge ncy DC 1 and 2 2
A A
Class IE Faer-Watts gency DC 1 and 2 2
A A
Class IE Emer-Loading Sequence Aux. Rel.
gency Pnt. Lights DC 1 and 2 1
Alarm CR Annunciator NA NA NA Non-Class IE Not Avstlable Per Vital DC DC 1 and 2 1
Alarm CR Annunciator NA NA NA Non-Class IE Trouble Per DC h
SHEET 18 0F 25 I
2 3
4 5
6 7a 7b 8a Rb 9
10 11 LOCATION QUALIFICATION NO.
INSTRUNENT ENVIRON-QUALITY REF.
OF RANCE HENTAL SEISNIC ASSURANCE POWER TYPE NO.
CAT.
VARI ABLE CHAN.
ISOVIDED SENSOR DISPEAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Power Su glies (Cont'd)
Emergency On-1 Indicating Switchgear CR RTGB B
A A
Class IE Emer-site 4 kV Bus Per Lights gency Tie Breakers Brkt.
Status Emergency On-1 Indicating Switchgear CR RTCB B
A A
Class IE Emer-site 4 kV Bus Per Lights gency Breakers Status Brkr.
Station Air 1
0-125 psig RAB CPI Indicator B
A NA Non-Class IE Pressure Vital e
Instrument Air 1
0-125 psig CR RTCB Panet B
A A
Non-Class IE CPI Indicator Supply Pressure Vital Nitrogen System Alarm Annunciator B
A NA Non-Class IE Trouble Vital Area Radiat ion e
P.
I I
Containment Area 2
RB El 99.5' (R Panet A
A A
Class IE Compli.-, with Condi-tions in G l.97 Radiation at 270* and CP-14A&B Notes 6 and 7 90*
- High R.a nge RE-CA 5400AS Indicators 6 I g/hr to 10 R/hr
& BS Recorders k
i R/hr to QS!1)S 8
2 x 10 R/hr A
)
's a
I
l SHrET 19 0F 25 a
1 2
3 4
5 6
7a 7b Ra 8b 9
to It 4
LOCATION (WALIFICATION NO.
INSTRUPENT ENVIRON-QUAL.lTY REF.
OF RANCE HENTAL SEISHIC ASSURANCE POWER TYRE No.
CA T.
VARIABLE CHAN.
I1t0VIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES
_ _ _ _ _ _. _ _ _ - _ _ _ _ _ _ _ = = =. -
- _ _ _ _ _ _ _ _ _ _ _ = = - = = -
Area Radiation (Cont'd)
E 2
2 Radiat ion Ex-1 IO-I R/hr
-Fost Accident CR Panel A
A A
Non-Compiles with Condt-0 posure Ra te (In-Per t o 10 R/hr Sampling Sys-CP 6 Class IE tions in RC 1.97 side Buildings A rea tem Area Vital Notes 6 and 7 or Areas where
-Diesel Cen.
Refer also to' Access is Re-Area 3A, Die-Variable Cl3 quired to Ser-sel Cen.
vice Equipment Area 38 m
Import an t to
-Elec t rical Safety)
Equipment Area
-Tur b. Dri ve EFW Pump Area
-Wast e and Boron Area i
-CCW Area Airborne Radio-active Materials Released From Plant E
3 2
Containment or Purge Ef fluent The Effluents are Dis-(Noble Cases charged through Common
)
and Vent Flow Plant Ve nt a.ul Mon t -
]
Rate) tored t here. See E7
?
a E
4 2
Reactor Shield Building Annulus The Effluents are Dis-charged through Common (Noble Canes Vent Flow Rate)
Plant Vent and Mont-tored t here. See E7 E
5 2
Auxillary Building (Noble The Effluents are Dis-Cases and Vent charged through Common Plant Vent and Mont-Flow Rat e) tored there. See E7
SHEET 20 0F 25 1
2 3
4 5
6 7a Jb Sa 8b 9
10 11 LOCATION quALIFICATIOJ ENVIRON-Qt!ALITY 4
NO.
INSTRUPEEN1 MENTAL SEISMIC ASSURANCE POWER
]
BEP.
OF RANCE TY PE NO.
CAT.
VARI ABLE CRAW.
PROVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES
~
l 1
1 Altborne Badjo-active Materfals Released From l
Plant (Cont'd)
E 6
2 Condenser Air 1
10 2 Ct /c c Turbine CP-52 in S
A NA Non-Complies with Condt-4 Class IE tions in RC 3.97 henovat System to Building Control Room Emer-Note 8 5 pct /cc Recorder i
Exhaust (Noble 10 gency 1
Cases and Vent 0-1101 Flow t
Flow Rate) 1 4 sC1/cc Plant Stack CP-52 in Control 5
A NA Class IE Compiles with Condt-E 7
2 Plant Stack 1
10 i
Monitor.
In-to Room Recorder Emer-tions in RC 1.97 cl.nles Contain-10*5 sect /cc gency Note 8.
Design Flow Range is 13,000 SCFM ment Purge 420%. Refer to PSAR Eifluent (E3),
Subsect. 1.9-29.1 Shield Butidig (NUREC 0737 Ites j
Annulus Exhaust II.F.1).
(E4), Auxtllary Butidtog Ef f-4 luent (ES), and Condenser Air 1
Pesoval Exhaust (E6)
Effluent radiation E
8 2
Ve nt from Atnos-level, Steam Cenera-pheric Dep ter Pressure versus Valves time strip charts and 1
Noble Cases I per 10* mr/br to RAB El +46 m Panel CP-52 B
A NA Mon-flow rate following i
Ra dia tion Main 105 ar/ fir Recorder Class IE MSlv closure is used Vital for estimating radio-Steam.
logical releases.
Line Calculat ton method-Steam Cenera-2 0-13fC pstg Inst. Cab. In CR RTC3 Panel A
A A
Class IE ology is described in i
I tor Pressure per Containment CP8 Indicators Vital FSAR Subsection SC
& Recorders (2) 1.9.29.4, Am. 33.
i 6
SHEET 21 OF 25 I
2 3
4 5
6 7a 7b Ra 8b 9
10 11 1.0 CATION QUALIFICATION NO.
INSTRUMENT ENVIRON-QdALITY RF.F.
OF RANCE MENTAL SEISMIC ASSURANCE P0bTR TYI'E NO.
CAT.
VARIABLE CHAN.
FROVIDED SENSOR DISPl.AY NOTE (1)
NOTE (2) tX)TE (3)
SUPPLY NOTES Airborne Radio-active Materials Released From Plant (Cont'd) 6 In Con-CR RTGB B
A NA Mon-Ve nt Flow Rate 1
0-8 m 10 Per Ib/hr t ainme nt Panel CP-1 Class IE Yital SC RecotJer 1
0-8 m 106 g, can.
CR RTCB B
A NA Mon-Per Ib/hr tainment Panel CP-1 Class IE Vital SC Indicator E
9 2
All Other Iden-titled Release Puf nts (Noble Case s and Ver.1 Flou Rate):
- Fuel Handl:? ng 1
10-6 uC1/cc FHB G Panel CP-52 B
A NA Non-Complies with Condi-Ruilding Post to Recorder Class IE tions in RG 1.97 Escr-Note 8.
Accident Moal-10*5 uC1/cc gency toring E
10 1
All Identified 3
Crab Sampl-EHB Radioches Lab 8
A NA Non-Complies wit h Condt-Class IE tions in RC 1.97 Plant Release ing as re-Note 13. See FSAR Points required in Subsection 1.9.29 for (Pa rt icula t es NOREC 0737 a detailed descrip-and Italogens)
II.F.I
- tton, at all re-lease points.
(Condenser vacuum Puep.
FHB Faergency Exhaust.
Plant ve nt Stack) 6
_ _=
1 SHEET 22 OF 25 4
1 I
2 3
4 5
6 7e 7b Sa 8b 9
10 11 t.OCATI(48 (PALIFICATION No.
INS 11tt; MENT Elt#1 ROM-QUALffT REF.
OF RANCE MENTAL SEISMIC ASSURANCE FOWER Tf f'E NO.
CAT.
VARIAELE CHAN.
Mt0VIDED SENSOR DISFLAY NOTE (1)
NOTE (2)
NOTE (3)
SUFFLY NOTES
.=
Environs Radla-t son.and Radio-j act tut ty l
1 Program which would be i
E 11 Radiation Es-followed to meet the l
posure Meters requirement of NUREC (Environs 0654 will be based on Radiation and Waterford 3 SES Radio-Radioacttutty) lostral Tech. Spec 3/4.11 & 12 and on tte Operational Environ-mental Monitoring Program FND-CO-20.
i E
12 3
Airborne Radio-NA 10-93C1/cc NA NA C
NA NA NA Portable Battery Fawered Instruments.
halogens and to Pa rt iculat e s 10-3 pc t/cc (Portable Sampl-Ing with Onsite Analysis capa-bility)
E 13 Plant and En-4 l
virons Radia-tion 3
l (Portable t
Instrument) a NA NA C
NA NA NA Portable Battery 4
j 3
Photons NA 10-3 g/hr Operated Instruments to 10 j
with Overlaping Ranges R /h r, Thotons l
?
memnums
SHFF.T 21 0F 25 e
1 2
3 4
5 6
la 7b 8a 8b 9
10 11 LOCATION QUALIFICATION j
NO.
INSTRUPENT ENVIRON-QUALITY REF.
OF RANCE NENTAL SEISMIC ASSURANCE POWER TYPE NO.
CAT.
VARI ABLE CHAN.
PROVIDED SEllSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES Environs Radia-t ton and Radio-activity (Cont'd) 3 BETA Radiations NA 10-3 Rads /
NA NA C
NA NA NA Range provided is and Low-Energy hr to 2.5x103 considered adequate.
Photons Ra ds/h r.
j Beta & Low-Ene rgy i
1 Photons E
14 3
Plant and En-NA NA C
NA NA Non-Stationary Hulti-J virons Radio-Class IE Channel Analyser is l
activity Used to Analyre Crah (Portable Samples.
)
Ins t rumen t a tio n)
Heteorology E
15 3
Wind Direction 3
0-360 degrees Primary Tower (2) CRT in CR Digital C NA NA Non-Hects Requirements of Backup Tower (1) Digital and chart Class IE RC 1.23/Rt and in Instrument NUREC 0564.Not resorded.
Shelters E
16 1
Wind Speed 3
0-50 meters / Primary Tower (2) CRT in CR; C
NA NA Non-Hects Requirements of see Backup Tower (1) Digital and Chart Class IE RC 1.23/RI. arkt in Instrument NUREC 0564. Not recorded.
Shelters E
17 3
Estimation of 3
TD (-5.0 t o Ptimary Tower (3) CRT in CR; C
NA NA Non-Heets Requirements of At mosphe ri c
+5.0*C)
Towers Digital and Chart Class IE RC 1.23/RI. and S t ah t lit y-S pl i t 2
ST (0-45 Backup Tower (2) in Instrument NUREC 0564. Niet recorded.
Sigma de grees)
Slwlter
-Temperature Dif ference (TD)
-Sigma Theta (ST) i
7 4
SHEET 24 0F 25 e
1 2
3 4
5 6
7a 7b 8a 8b 9
10 11 LOCATION QUALIFICATION NO.
I NSTRUKENT ENVIRON-QUALITY REF.
OF RANCE MENTAL SEISHIC AS SURANCE POWER TY PE No.
CAT.
VARI ABLE CHA N.
PR OVIDED SENSOR DISPLAY NOTE (I)
NOTE (2)
NOTE (3)
SUP PLY NOTES
.mmm..m.mm________-..
m--.--- - - - - m
-mo.....
Primary Coolant Compiles with re-and Sump - Crab quirements in Sanple RG 1,97 Notes 5 an.1 18 Hects Require-ments of NUREC 0737 F.
IR 3
Cross Act ivit y NA 10 pCl/ml to NA NA C
NA NA Non-Item Ill.B.3.
Refer 10 Cl/ml Class IE t o FS AR Su ber t ion Eme rgency 9. 3.H. " Post Accident Sampling System."
F.
19 3
Camma Spec trum NA Isotopic NA NA C
NA NA Non-Analysis Class IE Eme rge nc y E
20 3
Boron Content NA O to NA NA C
NA NA Non-6000 pre Class IE Eme rge ncy E
21 3
Chloride Cos tent NA O to 20 ppm NA NA C
NA NA Non-Class IE Emergency E
72 3
Dissolved NA 0 to 2000 NA NA C
NA NA Non-Hydror,en ec( STP)/k g Clans IE Eme rge ncy E
23 3
Dissolved NA 0 to 20 ppm NA NA C
NA NA Non-Oxygen Class IE Eme rge nc y E
24 3
pH NA I to 13 NA NA C
NA NA Non-Class IE Eme rgenc y
SHEET 25 OF 25 7
2 3
4 5
6 Ja 7b Sa Sh 9
10 11 LOCATION QUALIFICATION ENVIRON-QUALITY NO.
INSTRUNENT MENTAL SEISNIC ASSURANCE POWER OF RANCE TYPE No.
CAT.
VARI ABLE CHAN.
ISOVIDED SENSOR DISPLAY NOTE (1)
NOTE (2)
NOTE (3)
SUPPLY NOTES REF.
Containment Atmosphere -
Crab Sample l
E 25 3
Hydrogen 1
0-101 Radio Chee lab Radio Ches Lab NA NA NA Non-Class IE Content (0-100% of Instr. scale)
E 26 3
0xygen 1
0-301 Radio Chee lab Radio Ches Lab MA NA NA Non-Class IE j
Content (0-100% of lostr. scale)
E 27 3
Caumna Spectrum 1
Suffielent Radio Chee lab Radio Ches Lab NA NA NA Non-class IE for Isotopic Analysis l
l t
- i v m
1 e
24?DW-0 e
TABLE 3 WATERFORD-3 EXCEPTIONS TO REC CUIDE 1.97 REV 2 RE(XHHENDAT IONS PE F NO.
VARI A BLE REO RIFENDAT ION WATER FOR D-3 roSITION Q-3 RCS Soluble Baron Range:
D-6000 ppm Range Provided:
10-5000 ppm.
Plant specific.
Concentration The boron concent rat ion will exceed ~ 300 pro f or most not 4
demanding operating mode.
9-7/R-ll RCS Pressure Rang e:
0-4000 psig Range Provided: 0-3000 psig.
Plant s pec i f ic,
c-4/C-9 Considered adequate rending resolution of ATVS issue.
D-6 Flow in llPSI Range: 0-110% of Range Provided:
0-400 gpm insignificant deviation.
System (Cold Irg) design finw (105% of design flow).
6 D-IR flain Steam Flow Range: 0-110% of Range Provided:
0-8 x10 Insignificant deviation.
Indication design flow lb/hr (106% of Nominal Flow)
D-25 Containment Sump Ra nge: 50F-250F Range Provided:
Plant s pec i f ic.
Water Temperature Based on plant specific analysis.
D-20 Component Cooling Ra nge: 32F-200F Range Provided: 32F-130F.
Plant Specific.
Wa ter Temperature Based on plant specific analysis to ESF System (See FSAR Table 9.2-9).
E-li Environs Radiation Ranpe:
10~3 - 10 Range Provided:
10 2.5x10' Insignificant elev iat ion,
and Radioactivity Rads /Hr pa,q s /llr Beta Radiation and Iow-Energy Photons
1 2420W-3 TABLE 4 WATERFORD-3 POST ACCIDENT MONITORING INSTRtINENTATION TO RE CROVIDED AFTER FUEt. LOAD INSTRUMENTATION AVAILAR11 AFTER MODIFICATION TD SCHEDULE FOR REF NO.
VARIARLE AT FUEL IAAD MEET RG 1.91 REV 2 MODIFICATION C-2/
Radioactivity A post-acclJent sampling system as described in FSAR 51 power in accordance C-3/
Concentration Subsection 9.3.8 vill be provided, it will be designed with SER Chapter 22 E-18 or Radioactivity to allow the operator to take a grab sample for analysis Item 11.B.3.
thru level in Circu-under post-accident conditions.
E-24 lating Primary Coolant C-13/
Radiation Fost-accident radiation The high range radiation Four of these instruments with E-2 Esposure Rate esposure ratep in t t*,
monitors that will be input to QSFDS will be available areas listed in Table 2 can provided are delineated by Fuel Imad. Remaining high be made by observing the in Table 2.
range radiation monitors will be background response witta available by Commercial Operation.
entsting detectors in that a rea.
Ttwee readings will provide general information on radiation levels. Specific information would then be ob-tained by the use of portable monitoring equipment.
h L -