ML20135A486
| ML20135A486 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/30/1985 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 SBN-864, NUDOCS 8509100173 | |
| Download: ML20135A486 (100) | |
Text
,. t SEABROOK STATION Engineering Office August 30, 198S O # SBN-864 T.F. B7.1.2 Mew Hampshire Yonkee Divleien United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH letter (SBN-384), dated November 24, 1982, " Meeting Notes, Instrumentation and Control Systems Branch (ICSB),"
J. DeVincentis to G. W. Knighton (c) PSNH letter (SBN-499), dated April 14,1983, " Response to Generic Letter 82-33; Supplement 1 to NUREG-0737,"
J. DeVincentis to D. G. Eisenhut
Subject:
Accident Monitoring Instrumentation Review and Compliance with Regulatory Guide 1.97
Dear Sir:
Please find enclosed; revised FSAR Section 7.5 (Attachment I), an addition to the FSAR-Appendix 7A (Attachment II), and a marked-up FSAR Section 1.8 (Attachment III), which indicate Seabrook Station's compliance with Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Revision 3. This information will be incorporated into the FSAR by a future amendment.
The guidance provided in Regulatory Guide 1.97 and ANSI /ANS-4.5,1980,
" Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors,"
endorsed by Regulatory Guide 1.97, was used in selecting the Seabrook Accident Monitoring Instrumentation (AMI). Specific exceptions to or deviations from this guidance, with the associated justifications, are provided in the revised FSAR Section 7.5 and Appendix 7A.
As a result of the AMI review, we are replacing and relocating sensors and making circuit modifications. These modifications will be completed prior to fuel load.
8509100173 050030 . 00 PDR F
ADOCK O g3 l i
P.O Box 300 . Sootxook.NH 03874 . Telephone (603)474 9521
. , . _ .. __ . __ ~ .. . . __. _. .. .. - _ _
.y, 'O United States Nuclear Regulatory Commission Attention:. Mr. George W. Knighton
. : Page 2 4 -
The enclosed completes our commitments made in RAIs 420.2, 420.49 and i
420.51, as well as that provided in FSAR Section 1.8, regarding Seabrook's compliance to Regulatory Guide 1.97. This also satisfies Generic Letter No. 82-33,. Supplement 1 to NUREG-0737, Requirement for Energency Response
- Capability, Item No. 6 [ Reference (c)]. Since any additional changes would
- adversely affect the project schedule, we request that you ' provide written '
notification of the acceptability of this submittal.byf September 30, 1985.
l Very truly y urs, m,
John'DeVincentis, Director Engineering and Licensing v Attachments i
cc: -Atomic Safety and Licensing Board Service List
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5 SBN-864 ATTACHMENT I (FSAR SECTION 7.5)
I J-I
e SB1&2
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- FSAR TABLE OF CONTENTS FSAR Section Title Page 7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION...................... 7.5-1 7.5.1 Introduction........................................ 7.5-1 7.5.2 Definitions......................................... 7.5-1 7.5.3 Discussion.......................................... 7.5-1 7.5.4 Accident Monitoring Instrumentation................. 7.5-4
. 7.5.4.1 Compliance with Regulatory Guide 1.97...... 7.5-4 7.5.4.2 Description of Variable Types.............. 7.5-5 7.5.4.3 Development of Accident Monitoring Instrument List............................ 7.5-6 7.5.4.4 Design and Qualification Criteria.......... 7.5-6 FSAR APPENDIX 7A Regulatory Guide 1.97, Revision 3 Deviations and Justifications 7.5-1
SB 1 & 2
- 7.5-1 Accident Monitoring Instrument List 1
7.5-2 Control Koom Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During
' Normal Operation Including Operational occurrences a
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7.5-11
O SB 1 & 2
- FSAR 7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION 7.5.1 Introduction Display instrumentation is provided in the Main Control Room to enable the operator to monitor plant status under all operating conditions and to take any necessary manual actions. This display instrumentation consists of analog and digital indicators, recorders, status lamps, indicating lights, Video Alarm System (VAS) alarms, video displays (CRT and plasma) and annunciators.
. Dispir.y instrumentation is also provided in the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) to support the functions to be performed by the personnel in the TSC/ EOF.
7.5.2 Definitions Design Basis Accident Events Those events postulated in the plant safety analyses, any one of which may
. occur during the lifetime of the plant, and those events not expected to occur, but postulated in the plant safety analyses because their consequences would include the potential for release of significant amounts of radioactive material to the environs. These events are listed in FSAR Chapter 15 as Conditions III and IV occurrences. Excluded are those events (defined as
" normal" and " anticipated operational occurrences" in 10CFR50) expected to occur more frequently than once during the lifetime of the plant.
Task Analysis Process of identifying and examining tasks that must be performed by the Control Room operating crew when interacting with the plant systems.
7.5-1 l
SB 1 & 2 FSAR 7.5.3 Discuccion An Accident Monitoring Instrumentation (AMI) list, Table 7.5-1, has been developed to define the instrumentation required by the operator for design basis accident events. The AMI enables the operator to mo..e safety functions, take any manual actions required to support the accomplishment of safety functions and to determine the effect of manual actions during and following a design basis accident event. The AMI also enables the operator to maintain the plant in a hot shutdown condition, or to proceed to cold shutdown. Details are provided in Subsection 7.5.4.
Table 7.5-2 lists additional information available to the operator for monitoring conditions in the reactor, the Reactor Coolant System, the containment and key process systems throughout all normal operating conditions of the plant, including anticipated operational occurrences.
Status lamp arrays are used to indicate both a demand for a protectlya function /ESF actuation and the appropriate valve position and equipment status for ESF actuations. These arrays are functionally arranged on the Control Board to enable the operator to quickly and accurately monitor system status.
Status lamp arrays are provided to monitor bistable trips for the following safety functions:
- 1. Reactor Trip
- 2. Safety Injection
- 3. Containment Isolation
- 4. Steam Line Isolation
- 5. Feedwater Line Isolation To monitor valve position, actuated equipment status and emergency power availability, status lamp arrays are provided for the following:
1 1. Cold Leg Injection
- 2. Cold Leg Recirculation
- 3. Hot Leg Recirculation 7.5-2 l
SB 1 & 2
. FSAR !
l
- 4. Containment Isolation, Phase A
- 5. Containment Isolation, phase B
- 6. Main Steam and Feedwater Isolation j 7. Cooling Tower Actuation i 8. Diesel Generator Status
- 9. Emergency Power Sequencer I
A computer-based Video Alarm System (VAS) is provided to alert the operator when various process limits are exceeded. The incoming alarms are prioritized l to allow the operators to focus on high priority alarms during major plant upsets. Three levels of priority have been established. Incoming alarms are also broken down into primary and secondary sides; primary side alarms are displayed on the alarm CRTs in Main Control Board Sections A and D, while
~
secondary side alarms are displayed on the alarm CRTs in Sections F and I.
Various CRT-based dynamic displays are provided to serve the needs of the operating crew. These displays supplement those described above. CRT-based displays are provided in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) to support the functions to be performed by the i personnel in the TSC/ EOF.
s The computer system consists of two host computers, each of which is fed from a separate uninterruptible power supply. An automatic failover scheme is
- provided. The remainder of the system is configured such that system peripherals can be manually aligned to the available UPS. ,
Annunciators back up the VAS should a complete Computer System failure occur.
The annunciators also have a limited "First Out" capability to assist the operator in determining the cause of a reactor trip or safety injection. A limited set of-essential parameters is monitored for the following:
?
- 1. Reactor Trip Signals
- 2. ESF Actuation signals !
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- 3. Certain Technical Specification Deviations i 4 Important Systems-7.5-3 n - - ,, , , - , - - . . . . - - - , - - - , ,, ,,,,,,,,,-,-,a- ,--,,-,,,-,-,,ne-,,-,---,
. - . = . . - . . . . . - _ . _ . _ - . - - - .
i SB 1 & 2
= FSAR I
i The Annunciators are powered from a vital instrument panel; this power source i
- is independent of the power supply for the VAS. ;
( Bypassed / inoperable condition of safety systems is displayed on the VAS and on status lamp arrays on the MCB - one per train. Refer to Subsection 7.1.2.6 for a complete discussion of compliance with Regulatory Guide 1.47.
7.5.4 Accident Monitoring Instrumentation
! 7.5.4.1 compliance'With Regulatory Guide 1.97 i
! Regulatory Guide 1.97 Revision 3 endorses, subject to certain clarifications, ANSI /ANS 4.5-1980, " Criteria for Accident Monitoring Functions in Light-Water-Cooled Nuclear Reactors." The guidance provided in Regulatory Guide 1.97 and ANS 4.5, with certain exceptions, and NUREG-0737 has been used in selecting the Seabrook Accident Monitoring Instrumentation (AMI).
! The exceptions to the guidance provided in Regulatory Guide 1.97 and ANSI /ANS j 4.5 are:
j l
- 1. Not all the variables recommended by Regulatory Guide 1.97, Table 3 have been included in the AMI List. Specific deviations and the associated 1 i justifications are provided in Appendix 7A.
l 2. Not all the AMI characteristics recommended by Regulatory Guide 1.97, Table 3 have been met. Specific deviations and the associated justifications are provided in Appendix 7A.
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- 3. The determination of performance requirements for AMI did not follow the guidance of Regulatory Guide 1.97 Section C.2.4 in that:
a) : Required accuracy of measurement was not determined in procuring. the i instrumentation. 'Instead, the accuracy of the as-procured instrumentation was determined and then reviewed for acceptability.
Further details are provided in Subsection 7.5.4.4.e.5.
7.5-4
.__ _ _ _ . . _ . u -_ . _ _ _ _ _ . _ . _ _ . . - _ _ . _ . _ . , _ _ . . _ . . _ . _ ,
SB 1 & 2 FSAR b) Response characteristics (time) have not been determined for instrumentation channels that provide monitoring functions only. The response time for these channels is similar to the response time determined for ESF actuation channels since similar hardware is used.
Therefore, determination of the response time for each channel is not necessary.
7.5.4.2 Description of Variable Types
- a. Discussion The accident monitoring variables are classified into five types (A, B, C, D or E) according to the monitoring function they perform. A definition of each type is provided in the following subsections.
- b. Type A Variables Type A variables for Seabrook Station are those variables to be monitored that provide the primary information for the Control Room operators to take specific pre-planned manual actions for which no automatic control is provided. These actions are required for safety systems to accomplish their safety function for design basis accident events. Actions taken as a result of equipment failures (e.g., the " Response Not Obtained" column in the Emergency Response Procedures (ERPs) are excluded,
- c. Type B Variables Type B variables provide the most direct indication to monitor the accomplishment of the CSFs. CSFs are those safety functions that are essential to prevent a direct and immediate threat to the health and safety of the public. The accomplishment of these functions ensures the integrity of the physical barriers against radiation releases.
7.5-5 i
SB 1 & 2 FSAR The six CSFs for Seabrook are:
- 1) Suberiticality
- 2) Containment Integrity (including radioactive effluent control)
- 3) Heat Sink
- 4) Core Cooling
- 5) RCS Integrity
- 6) RCS Inventory
- d. Type C Variables Type C variables provide the most direct indication of the potential for or the actual breach of the barriers to fission product releases. These barriers are: fuel cladding; primary coolant pressure boundary, and containment.
- e. Type D Variables Type D variables are those variables that provide information to indicate the operation of individual safety systems and nonsafety systems used in the .
1 mitigation of design basis accidents.
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- f. Type E Variables Type E variables are those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases.
7.5.4.3 Development of Accident Monitoring Instrun.ent List As part of the Detailed Control Room Design Review (DCRDR) a task analysis was performed on the ERPs to identify the needed instrumentation and controls to support the execution of these procedures. For each instrument needed, a determination of the variable type was made based on its use in the ERPs and the definitions for each variable type. The task analysis included the ERP contingency guidelines (ECAs); instrumentation used only to support the execution of the ECAs is not considered AMI.
7.5-6
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SB 1 & 2
- FSAR For each variable, a determination is made whether it is a key variable or backup variable in accordance with the following criteria:
Key variables are those variables that provide the primary information rectaired to permit the Control Room operating crew to:
- 1. Perfoon the diagnosis specified in the ERPs for design basis accidents.
- 2. Take any manual action required to mitigate the consequences of an accident.
- 3. Monitor the operation of safety systems.
Primary information is information that is essential for the direct accomplishment of the specified safety functions.
Backup variables are those variables that also provide information in addition to the key variables to assist the Control Room operating staff in:
- 1. Performing the diagnosis specified in the emergency operating procedures for design basis accidents.
- 2. Taking any manual actions required to mitigate the consequences of an accident.
- 3. Monitoring the status of individual components and ESF demand signals.
- 4. Resolving instrument ambiguity.
7.5-7
SB 1 & 2 FSAR Variables are then assigned a design category using the following matrix:
Design Category Variable Key Backup Type Variables Variables A 1 3 B 1 3 C 1 3
^
D 2 for safety systems 3 3 for nonsafety systems 3 E 3 3 The AMI list contains the instrumentation classified as Design Category 1 and 2, the instrumentation identified to monitor the performance of safety systems (Type D, Design Category 2) and Design Category 3 instrumentation included in Regulatory Cuide 1.97, Table 3. Revision 3.
7.5.4.4 Design and Qualification Criteria
- a. Discussion The AMI are assigned design categories as discussed in Subsection 7.5.4.3.
The design and qualification criteria for each design category are provided in the following subsections.
- b. Design Category 1 - Design and Qualification criteria
- 1. Equipment Qualification Design Category 1 instrumentation is environmentally qualified in accordance with IEEE 323-1974 and associated daughter standards. This instrumentation is seismically qualified in accordance with IEEE 344-1975. Further details on the methods used and compliance with associated regulations and Regulatory Guides are provided in Sections 3.10 and 3.11 of the FSAR.
7.5-8
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SB 1 & 2 1 , FSAR I 2. Redundancy No single failure within the AMI, its auxiliary supporting features, or its power sources concurrent with the failures that are a condition or result of a -
specific accident,' will prevent the operators from being presented the information necessary to determine the safety status of the plant and to bring the plant to and maintain it in a safe condition following that accident. The electrical independence and physical separation of redundant channels is discussed in Sections 8.3 and 7.1.
4 Where failure of one accident monitoring channel results in information ambiguity (i.e., the redundant displays disagree) that could lead operators to I l defeat or fall to accomplish a required safety function, backup information is provided to allow the operators to deduce the actual conditions in the plant.
This is accomplished by providing additional independent channels of information of the same variable (an identical channel) or.by providing an I independent channel to monitor a different variable that bears a known
! relationship to the multiple channels (a diverse channel). Information on
! redundant / diverse channel availability is included in the operator training
) program.
1 For systems having redundant components, single channel monitoring of the i
redundant parts of the system is provided. Verifying the proper functioning of one of the redundant parts of the system is sufficient to monitor the accomplishment of the safety function.
i-
- 3. power Source
^
Design Category 1 instrumentation is powered from safety-related uninterruptible power sources.
- 4. Availability i 2
1 The Design Category 1 instrumentation channels will be available prior to an l f
l accident except for testing and maintenance as provided in paragraph 4.11 of l IEEE Standard 279-1971 or.as specified in the-Technical Specifications.
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- 5. Quality Assurance Quality Assurance for Design Category 1 instrumentation is provided in accordance with the QA Program described in Chapter 17 of the FSAR.
Conformance to appropriate regulatory guides is discussed both in Chapter 17 and Section 1.8 of the FSAR.
- 6. Display and Recording Indication: For design Category 1 variables, continuous, redundant indication is provided. This indication meets the applicable requirements for design Category 1 instrumentation.
Recording: Recording of instrumentation readout information is provided for at least one of the redundant channels.
1 Trend Indication: Where direct and immediate trend or transient information is essential for operator information or action, this information is available from multiple displays such as:
- 1. Dedicated recorders, or 4
- 2. Dedicated ratemeters, or
- 3. CRT displa;- (via the plant computer) available on demand, or
- 4. Plasma displays - available on demand by use of dedicated function push buttons.
For trend display channels, at least one of the display devices meets the applicable requirements for design Category 1 instrumentation.
I 7.5-10 1
- 7. Identification Types A, B, and C instrumentation displays provided for operator use during accident conditions are identified by an orange nameplate containing black letterir.g.
- 8. Interfaces The transmission of signals to the accident monitoring equipment from protection equipment is through isolation devices which are classified as part of the protection system.
No credible failure at the output of an isolation device will prevent the associated protection channel from meeting the minimum performance requirements considered in the design bases. Examples of credible failures include short circuits, open circuits, grounds, and the application of the maximum credible ac or de potential (140 V de or 129 Y ac). Refer to FSAR Subsection 7.2.2.2.c.7 for further discussion.
- c. Design Category 2 - Design and Qualification Criteria
- 1. Equipment Oualification Design Category 2 instrumentation is environmentally qualified in accordance with IEEE 323-1974 and associated daughter standards. Further details on the methods used and compliance with associated regulations and Regulatory Guides are provided in Section 3.10.
- 2. power Source Design Category 2 instrumentation is powered from highly reliable power sources, very often Class 1E. Where momentary power interruption is not tolerable, uninterruptible power sources are used.
I 7.5-11 i
SB 1 & 2
- 3. Quality Assurance Quality Assurance for Design Category 2 instrumentation is provided by United Engineers and Constructors for the design, procurement and installation phases. Their QA Program contains the measures necessary to insure that the instrumentation has been properly specified, procured and installed. This program contains the applicable elements of 10CFR50, Appendix B.
Quality Assurance for the testing Ph ase is provided by the standard testing procedures of the NHY Startup and Test Department. Auditable records are available for each Design Category 2 instrument.
Quality Assurance during the operational phase is provided under the NNY Operational Quality Assurance Program (OQAP). Further details are provided in Subsection 17.2.
- 4. Display and Recording Indication For Design Category 2 instruments, either display on demand or continuous indication is provided.
Recording Effluent radioactivity and area radiation variables are recorded.
Trend Indication Where direct and immediate trend or transient information is essential for operator information or action, trend indication is provided. This indication consists of either dedicated recorders or CRT displays.
7.5-12
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=
- S =
P 5. Identification
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Types A, B and C instrumentation displays provided for operator use during
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-g accident conditions are identified by an orange nameplate containing black -A
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_smuum-lettering. q d2EIS-E
- 6. Channel Availability d g M
""Es G
Design Category 2 instrumentation channels will be available prior to an
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\accidentasprovidedintheplantadministrativeprocedures. W-
- 7. Interfaces _s 1
-A N Same as Design Category 1.
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- d. Design Category 3 - Design and Qualification Criteria -
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- 1. Quality Assurance This instrumentation is of high-quality commercial grade and is selected to lW withstand the expected plant service environment.
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- 2. Display and Recordinx -
_ Indication y
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c t The information display can be either continuous or available on demand.
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- Recording g
M I Effluent radioactivity variables and meteorological variables are recorded. m
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- 7*5~13
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l SB 1 & 2
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operation information or action, trend information is provided. Trend information may be from a dedicated recorder or available on demand from the
)
plant computer system.
i
- e. Design and Qualification criteria Applicable to Design Categories 1. 2.
and 3 i
- 1. Range I
The range of the readouts extends over the maximum expected range of the variable being measured. Where two or more instruments are needed to cover a particular range, overlapping of the instrument spans is provided.
.2. Servicina. Testina. and Calibration Means are provided for checking, with a high degree of confidence, the I
operational availability of each sensor during reactor operation.
i This may be accomplished in various ways, for' example:
i
- 1. By perturbing the monitored variable; or
? 2. By introducing and varying, as appropriate, a substitute input to the sensor of the same nature as the measured variable; or 1
! 3. By cross-checking between channels that bear a known relationship to 5
each other and that have readouts available.
4 3 The AMI is designed to permit any channel to be maintained when required i
during power operation.
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1 -
7.5-14
_._.._ _ , ,. _ . - _ . _ _ . . _ _ , _ _ _ _ . . . _ . . . . . _ . _ .l
6 SB 1 & 2
- 3. Human Factors The AMI is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules. The AMI is designed to minimize the development of conditions that cause meters, annunciators, recorders, etc., to give anomalous indications potentially confusing to the operator.
The displays are functionally arranged on the control board to provide the operator with ready understanding and interpretation of plant conditions.
Comparisons between duplicate information channels or between functionally related channels will enable the operator to readily identify a malfunction in a particular channel.
In accordance with the guidance provided in NUREG-0737, an integrated effort for both the Detailed Control Room Design Review (DCRDR) and the AMI review was undertaken. The results of this effort identified the instrumentation needed by the operating crew during the course of an accident or in the recovery phase. The DCRDR reviewed the adequacy of these instrumentation displays for use by the operating crews against human factors criteria. The AMI review determined the adequacy of instrumentation channels against the design criteria stated in this subsection. Changes made after the completion of the DCRDR will be subjected to human factors review.
- 4. Direct Measurement To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables. Indirect measurements are generally used to provide backup information only.
- 5. Instrument Accuracy The plant-specific background documents prepared for the ERPs verify and document that the installed AMI has sufficient accuracy to support the ERPs.
j The accuracy of the AMI is addressed as part of the Operator Training Program.
7.5-15 __ ,
s J.
. g (DENT MONJTQe1NGj NSTRurENTATION LIST DATA TABLE LECEND AND NOTES Abbreviations:
c EOF Emergency Operations Facility l MCC f90 tor Control Center 19CR Main Control Room TSC Technical Support Center UPS Uninterruptible Power Supply Esplanatory Note 3:
A. Under the " Actual Range" column:
The calibrated range of the sensor is listed unless otherwise noted.
- 8. Under the " Redundancy" column:
"Yes" means redundant fully qualified displays are available in the MCR.
For Design Category 2 and 3 instrumentation, this column is marked "N/A" since there are no redundancy requirements for this instrumentation.
C. Under the " Power Supply" column:
The type of power supply for the instrumentation channels is listed.
Since there are no specific provisions for the power supply for Design Category 3 instrumentation, "N/A" is marked in this column.
O. Under the " Display" column:
The tag number of the available NCR display instrumentation is listed.
For the TSC/ EOF, display will be via CRT's driven by the Main Plant Computer System (MPCS). Where an analog input to the MPCS is provided, its corresponding analog input number is specified. Where a digital input is provided, its corresponding digital input number is specified.
E. Under the "S8 Category" column:
The plant-specific design category for this instrumentation as determined from the review described in Subsection 7.5.4, is listed.
F. Under the " Environmental Qualification" column:
"Yes" means the instruaerntation is included in the environmental qualification pregram. The appropriate requirements for each instrument are determined as part of this program. For Design Category 3 instrumentation, "N/A" is entered since there are no specific provisions for environmental qualification.
t 4o ACCIDENT MONITORING INSTRUMINTATION LIST
. DATA TASLE LEGEND AND NOTES (cont'd)
G. Mer the " Seismic Qualification" column:
"Yes" means that the instrumentation has been seismically qualified in accordance with the criteria stated in Subsection 7.5.6.
For Design Category 2 and 3 instruments, "N/A" is entsred since there are no specific provisions for seismic qualification.
H. Under the "QA" column:
"Yes" means the instrumentation meets the QA requirements detailed in the Design Criteria section for the applicable Design Category.
~I. Under the " Trending" column:
"Yes" means that trend or transient information is required for operator information or action based on our review of the plant-specific emergency response procedures and is available. "N/A" means that trend or transient information is not required for operator information or action based on our review of the plant-specific emergen:y response procedures.
J. Under the " Remarks / Notes" column:
For each item number,' any column entry with an asterisk is explained in the " Remarks / Notes" column.
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ACCIDENT MONITORI?O INSTRUMENT"rTION LIST .
DISPLAY R.G. 1.97 R.G. 1.97 MCR ITEM RECOMMEMOED DESIGN ACTUAL POWER TREMO TSC. EOF ,
MUMRER VARIABLE / SENSOR RANGE CATE CORY PANCE REDUNDANCY SUPPLY VARIABLE INDICATION COMPUTER PLANT-SPEC 1 TIC TYPE A VARIABLES C1 Degrees of Subcooling 2000 F subcooling 1 +3000F Yes Vital RC-TI-9424A RC-MM-7315 Available RC-PT-403 to 350 F superheat subcooling to UPS RC-TI-94248 - Through RC-PT-405 (from BIO) 500f Data Link
- IC-TE-1 through 58 superheat A2 Steam Generator From atmospheric 1 0-1300 psig# Yes Vital Pressure pressure to 20% UPS F W-PT-514 SG#1 above the lowest PI-514A MR-501 A0730 fW-PT-515 safety valve setting PI-515A -
A0733 (1425 psig)
FW-PT-524 SG#2 (from Die) PI-5244 -
A0740 FW-PT-525 PI-525A MR-502 A0743 FW-PT-534 SC#3 PI-5344 MR-503 A0750 FW-PT-535 PI-535A - A0753 FW-PT-544 SG#4 PI-544A -
A0720 FW-PT-545 PI-545A MR-504 40723 o
03 Core Exit Temperature 2000 F 0 to 2300 F 1 0-23000F# Yes vital RC-TI-9423A RC-MM-7315N# Available IC-TE-1 through 58 (from B8) UPS RC-TI-94238 - Through RC-MM-7315 Data Link A4 Steam Generator Level From tube sheet to 1 Taps 348" and Yes Vital a+
FW-LT-519 (MR) SG#1 separators 581" above UPS LI-519 (MR) LR-519(2) 4o734 FW-LT-501 (WR) (from D17) bottom LI-501 (WR) - 40737 reference for e
FW-LT-529 (NR) SG#2 narrow range. LI-529 (NR) LR-529(2) no744 FW-LT-502 (WR) Taps near tube LI-502 (WR) - 40747 sheet and above FW-LT-537 (NR) SG#3 separators for LI-517 (NR) LR-539(2) A0756 fW-LT-503 (WR) wide range. LI-503 (WR) - A0757 FW-LT-548 (NR) SC#4 LI-548 (NR) LR-549I2) A0725 fu-LT-504 (WR) LI-504 (WR) - A0727 A5 Pressurizer Level Bottom to top 1 Taps 6" from Yes vital -
RC-LT-459 (from D12) the top and UPS LI-4594 LR-459mu A0332 RC LT-460 bottom of the LI-460A L R -4 60 A0333 straight shell
- portion of the pressuriser#
TABLE 7.5-1 (Sheet 1 of 36)
m _. .. . - . _ -
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S8 ,
ITL M DESIGN ENVIRONMENTAL Si lSMIC NUMBER VARIABLE CATEGORY QUALIFICATION QUAL. QA TRLWOING REMARNS/ NOTES PLANT-SPECIFIC
- TYPE A VARI ABL ES R1 Degrees of Subcooling 1 Yes Yes Yes Yes A2 Steam Generator 1 Yes Yes Yes YesNN # See Deviation No, I in Appendia 7A.
Pressure em Trending required based on use as a Type D variable. ,
C3 Core Exit Temperature t Yes Yes Yes Yes # Sensors are type M thermocouples that are calibrated to 1650 0F.
- Individual sensor temperatures and spatial displays are provided on RC-xx-7315.
A4 Steam Generator Level ! Yes Yes Yes N/A A5 Pressurizer Level 1 Yes Yes Yes Yes # See Deviation No. 2 in Appendia 7A.
- The input signal to LR-459 is selectable to any one of the pressurizer level channels.
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TABLE 7.5-1*
(Sheet 2 of 36)
.. ,- _-. ~ . - - _ - - . . .
f a DISPLAY ,
R.C. 1.9 7 - R.G. 1.97 MCR ITEM RE COMME NDED DESIGN ' ACTUAL POWER TREND TSC, EOF NUMBER VARIASLE/ SENSOR RANGE CATEGORY RANGE REOUNDANCY SUPPLY VARIA8tE INDICATION COMPUTER .,_
A6 BWST Level .
Top to botton 1 22,000 to N Yes Vital
- Storage Tank Level (from 09) 406,000 gal- UPS CBS-LT-2300 LI-2300 LR-2304 A0912 CBS-LT-2383 LI-2303 LR-2305 40913 ,
A7 RCS Pressure O to 3000 psig i D-3000 psig Yes. Vital RC-PT-403 (from ett and 87) UPS PI-403 PR-403 A0350
- RC-PT-405 PI-405 PR-405(2) A0349 As Containment Hydrogen. O to 10% volume 1 0-80% H2 Yes. Vital ,
Concentration. (capable of operating '
0-20% 842 UPS CGC-AIT-58204 from -5 psig to dual range AI-SS20A# AR-58284 A1445 CGC-AIT-58288 manimum design -5 psig to AI-58288a -
A1446 pressure 52 psig) 60 psig (from C10) operating-capability RE ACTIVITY 'C2WTROL - -
Neutron Flus 10-61 to 1005 St 1 10-8-200% Yes Vital WI-NE-6690 full power Full Power UPS NI-6690-1 -
A1018 NI-NC-6691 -
NI-6691-1 - A1019 *
-1 to +7 DPR -
NI-6690-2 AIO21 (Rate) -
NI-6691-2 A1022 82 Control Rod Position Full in or not 3 0-220 N/A N/A CP-O-7330 full in Steps UI-7338 - 10036 through.
(Full in to 10091 fully.
withdrawn)
- ~
53 RCS Soluble Soron 0 to 6000 ppe 3 0-6000 ppm N/A N/A - - -
- Concentration #
(Grab Sample) ,
84 RCS Cold Leg Water 50*F to 400*F 3 See 96 Temperature O
w.
4
=
TABLE 7.5-1 (Sheet 3 of 16)
e* .
SR 11EM DESIGI ENVIRONMENTAL SEISMIC NUMBER VARIASLE CATEGORY QUAtJf1Cg10N QUAL. QA TRENDING REMARMS/ NOTES A6 RWST Level 1 Yes Yes Yes N/A # See Deviation No. 3 in Appendia 74.
Tank Level A7 RCS Pressure 1 Yes Yes Yes Yes 48 Contairunent Hydrogen 1 Yes Yes Yes N/A # See Deviation No. 4 in Appendin 7A.
Concentration REACTIVITY CONTRot.
31 Neutron Flun 1 Yes Yes Yes Yes 82 Control Rod Position 3 N/A N/A Yes N/A # Control rod position inputs to the computer are available but are not listed here.
83 RCS Soluble Boron 3 N/A N/A Yes N/A # See Deviation No. 5 in Appendia 7A.
Concentration #
B4 RCS Cold Leg Water See B6 Temperature 9
TABLE 7.5-3 (Sheet 4 of 36)
t e o,
DISPLAY R.G. 1.97 R,G, 1.97 MCR ITEM . RECOPT1 ENDED DESIGN ACTUAL POWER TREND TSC. EOF NUMBE R VARIA8tE/ SENSOR RANCE CATECORY RANCE REDUNDANCY SUPPLY VARIABLE It01CAi!04 COMPUTER ,,
CORE COOLI4G ,,
85 RCS Hot Leg Wter 500 F to 7000 F 4 0-7000F 40# Vital Temperature UPS
- RC-TC-4134 TI-413A TR-413A A0319 RC-TE-423A TI-4234 -
A0340 BC-TE-433A TI-433A(I) TR-433A(2) no34g RC-TE-443A TI-443A(I) - A0342 86 RCS Cold Leg w ter 500F to 7000F 1 0-700 0 F mon vital Temperature UPS RC-TE-4138 TI-4138 TR-4138 A0343 BC-TE-4238 TI-4238 -
A0344 RC-TE-4338 TI-4338(I' TR-4338(2) A0345 RC-TE-4438 TI-4438(4) - .A0346 87 RCS Pressure 0-3000 psig 1 See A7
, 88 Core Exit Temperature 2000 F to 23000 F 3 See A3 89 Reactor Coolant Inv. Bottom of hot leg 1 0-120% Yes Vital
-Reactor Vessel Full to top of wessel; (Full range: UPS Range Level (RCPs not bottom to top running).. of vessel)
RC-LT-13tl RC-LI-1311 RC-MM-7315 Available RC-LT-1312 RC-LI-1312 - Through Data Link
-Reactor Vessel- Void trending 0-120% (dynamic Dynamic Head head range; (RCP's running) indicates RC-LT-1321 normalized core RC-LI-1321 RC-MM-7315 Available RC-LT-1322 dp) RC-LI-1322 - Through Data Link 810 Degrees of Subcooling 200 0F subcooling 2 See'A1 to 350 F superheat -
RCS INTEGRIE 811 #CS Pressure O to 3000 psig 1 See A7 812A Containment Drainage Top to Sotton 2 Sump Water Level.
marrow Range #
4I TA88.E 7,5-1
.(Sheet 5 of 36) 1
e' o
- a SB 11EM DES tGal ENVIRONMENTAL SF.ISMIC NUMBER VARIA8LE CATEGORY OUALIFICATIO81 QUAL. QA TREN01mG RIMARNS/ NOTES CORE COOLING o
05 RCS Hot Leg Water 1' Yes Yes Yes Yes # All channels powered from UPS-I-A.
Temperature See Deviation Iso. 6 in Appendia 7A.
56 BCS Cold Leg Water 1 Yes Yes Yes Yes e All channels powered from UPS-I-B.
Temperature See Deviation No. 7 in Appendix 74.
OF RCS Pressure - See A7 Be Core Exit Temperature See A3 89 Reactor Coolan+. Inventory 1 Yes Yes Yes Yes 100% equals top of vessel or normal core dP with four reactor coolant pumps running.
810 Degrees of Subcooling See At RCS INTEGRITY BIl RCS Pressure See A7 912A Containment Drainage Suep # See Deviation No. 23 in Appendia 74.
Water Level, harrow Range #
~
TABLE 7.5-1 (Sheet 6 of 36)
m_ . _ . . _ _ . . . - _ _ _ . . __ _-
.' o DISPLAY R.G. 1.97 R.G. l.97 MCR ITEM REC 0f9tNDED DESIGN ACTUAL POWER TREND TSC, EOF NunSER VARIASLE/ SENSOR RANGE CATEGORY RANGE REDUNDANCY SUPPLY VARIA8tE ICICATION COMPUTE _R 5128 ' Containment Building (plant-specific) 1 4" to t'4" Yes Vital Level Wide Range above base UPS CBS-LIT-2304 elevation LI-2304 LR-2304 40930 CBS-LIT-2385 LI-2305 LR-2305(2) nog 3g CONTAI8pfET INTEGRITY 513 Containment Pressure O to design pressure 1 0-60 psig Yes Vital.
SI-PT-934, (52 psig) UPS PI-934 PR-934 A0500 SI-PT-935 PI-935 PR-935 A0501 014 Containment Isolation Closed-not closed 1 Closed- Yes# Vital ## -
Valve Position not closed DC See FSAR Section 6.2.4 eM Table 6.2-83
' for complete information on the design of the Containment Isolation System and the listing of individual containment isolation valves.
315 Containment Pressure -5 psig to design 1 See Cl!
SI-PT-2576 pressure (52 psig)
SI-PT-25??
(H).5 in WC Yes B16 Containment Enclosure - - Vital
< Negative Pressure UPS EAH-PDT-5702 PDI-5782 A377s Em+-PDT-5789 PDI-5789 A3779 517 Mein Steam - - Open(Closed Yes. Vital 2L-3005 -
D5222 Isolation Valve UPS 2L-1006 -
D5224 Posi'lan 2L-3007 - 05226 MS-V-6, 2L-3008 - D5220 MS-V-98 CS-3005 -
MS-V-90 CS-3006 -
~
MS-V-92 CS-3007 -
Cv3000 -
Big Feedwater Isolation - - Open/ Closed' Yes Vital CS-4212-1 -
04057 Valve Position DC CS-4222-1 - D4059 fW-V30 .CS-4232-1 -
04861 FM-V79 ' CS-4242-1 -
.04063 FWV40 CS-4212-4 - -
FWV57 CS-4222-4 - -
CS-4232-4 - -
CS-4242-4 - -
TA8LE 7.5-1 (Sheet 7 of 36)
< e
-~
~
. S8 ,
MITEM DESIGN ENVIRONME NTAL SFISMIC NUMBER VARIA8LE CATEGORY QUALIFICATION QUAL. 04 TREN0!NG REMARNS/ NOTES a
8128 Containment Building Level, I ~
Yes Yes Yes Yes Wide Range ,
_CONTA!IMENT INTEGRITY r
813 Containment Pressure 1 Yes Yes Yes- Yes 814 Containment Isolation 1 Yes Yes Yes N/A. e The redur.dancy provision for containment-Valve Position -
isstation valves is met on a systems basis, me The primary indications of containment isolation valve position are status lamp .
arrays arranged on a functional basis. A tile is provided for each valve closed on either a Phase A or Phase 8 containment isolation signal. Valve position.
indicating lighte-are also provided with each valve control switch.
815 Containmer.t Pressure See C11 816 Containment Enclosure 1 Yes Yes Yes N/A Negative Pressure 817 Main Steam Isolation 1 Yes Yes Yes N/A Valve Position Ole Feedmater Isolation 1 Yes Yes Yes N/A Valve Position j
l 1
T ABLE 7.5-1 (Sheet 8 of 16)
O oa o' .
DISPLAY R.C. 1.97 R.G. 1.97 MCR ITEM- RECOPT1[NDE D DESIGN ACTUAL P')WE R TREND TSC, EOF g NUM8ER VARIA8LE/ SENSOR RANGE CATE GORY RANGE REDUNDANCY SUPPLY VARIABLE INDICATION COMPUTER
. FUEL CL ADOING C1 Core Enit Temperature 2000 F to 21000 F .1 See A3 o
C2 Radioactive Concen- 1/2 Tech Spec limit 1 tration or Radiation to 100 times Tech Level in Circulating Spec limit Primary Coolante (50 to 10 4 uci/ge)
C3 Analysis of Primary 10 uCi/ml to 1 See EIS Coolant ( h to uCi/mi Spectrum) TID-14844 source s term in coolant volume
. RCS eOUNO.3Ry C4 RCS Pressure O to 3000 psig 1 See A7 CS Containment Pressure -5 psig to design 1 See C11 pressure (52 psig)
C6A Containment Drainage Top to bottom of 2 See 812A Sump Water Level sump Marrow-Range C68 Containment Reci*c' Wide-Range 1 See 8128 lation Sump Wat* (plant-specific)
Level, Wide-Rarr-C7 Containment Area a A/hr to 104 R/hr 3 See El Radiation C8 Effluent Radioactivity 10-0 uCi/cc to 3 See E7 Noble Cat Eff; sent 10-2 uC1/cc' from Co.Menser Air Removal System Enhaust CONTAINME,NT C9 RCS Pressure O to 3000 psig 1 See A7 C10 Containment Hydrogen 0 to 10% volume 1 See At~
Concentration (capable of
-5 psig to manimum design pressure (52 psig) t' T ABLE 7.5-1 i (Sheet 9 of 36)
-7 _
o o*
S8
'11FM ' DESIGN ENVIRONMrNTAt. GFISMIC NUM8FR VARIA8LE CATE GORY QUALIFICATION QUAL, 96 TREN01NG REMARNS/ NOTES FUEL CLA00lNC C1 Core Exit Temperature See A3 C2 Rad'ioactive Concentratton e Sete Deviation No. 8 in Appendia 7A.
or Radiation Level in Circulating Primary Coolant #
C3 Analysis of Primary See E18 Coolant (gamma spectrum).
RCS BOUNDARY C4 RCS Pressure See A7 CS Containment Pressure See C11 C6A Containment Drainage Sump See 812A Water Level. Narrow-Range C6B Containment Recirculation See 8128 Sump Water Level.
Wide-Range C7 Containment Area See El Radiation C8 Effluent Radioactivity See E7 Noble Gas Effluent from Condenser Air Removal System Enhaust CONTAIRMENT .
C9 RCS Prespure See 87 C10 Containment Hydroaen See AS Concentration TA8LE 7.5-1 (Sheet to of 36)
< a*
DISPLAY R.G. 1.97 R.G. 1.97 MCR IIEM RECOMME NDED DESIGN ACTUAL POWER 1 REND TSC, EOF WUMBER VARI 48LE/ SENSOR RANGE CATEGORY RANGE REDUNDANCY SUPPLY VARIABLE INDICATION COMPUTER Ct! Containment Pressure -5 psig pressure I (-)5-0-160 psig Yes Vital SI-PT-2576 to 3 times design UPS PI-2576 PR-934 A0517 SI-PT-2577 pressure for PI-2577 PR-937 A0516 concrete ,
(-5 to 156 psig)
C12 Containment Effluent 10-6 uCi/cc to 2. See E7 .
Radioactivity - Noble 10-2 uCi/cc Gases from Identified Release Points' C13 Effluent Radio- 10-6 uCi/cc to 2 10I -106 cp m N/A Emerg, activity Noble Gases 103 uCi/cc (corresponds to NOC (inside buildings or 6 a 10-4 uci/cc areas where pene- to 10 uci/cc) trations or hatches are located)
RM-RE-6566 RM-6566 - Available Through +
Data Link TYPE D VARI A8tES, SYSTEM OPERATION ,
gH,3 D1 RHR System Flow 0 to 110% design 2 0-5000 gpm N/A Vital RH-FT-618 flow (4950 gpm) UPS FI-618 -
A0950 RH-FT-619 FI-619 -
A0952 ,
D2 RHR Heat Enchanger 400 F to 350 0F 2 50-400 FM N/A Outlet Temperature Vital -
TR-612 A0954
- RH-TE-604 UPS -
TR-613 A0955 RH-T E-605
' ~
SAFETY INJECTION 4.
D3 Accumulator Tank 10% to 90% volume 2 Leve1#
D4 Accumulator Tank 0 to 750 psig 2 Pressure #
TABLE 7.5-1 (Sheet 11 of 36)
_ .. . 4 . _ . _ _ . _ . . . _. __m ._ . . _ . _ _
e ,*
$8 ITEM DESIGN ENVIROGRW NTAL SEISMIC NUMBER VARIABLE CATEGORY QUALIFICATI0ef QUAL. QA TRENDING REMARNS/ NOTES C11 Containment Pressure 1 Yes Yes Yes N/A C12 Containment Effluent See E7 Radioactivity - Noble Gases from Identified Release Points C13 Effluent Radioactivity. 2 Yes N/A Yes N/A e See Deviation No. 9 in Appendia 7A.
Noble Gases (inside buildings or areas where penetrations or hatches are located)
TYPE D VARIAOLES. SYSTEM OpfRATION EH_8 01 RHR System Flow 2 Yes N/A Yes . N/A D2 RHR Heat Enchanger 2 Yes N/A Yes N/A e See Deviation No. 22 in Appendia 7A.
Outlet Temperature SAFETY INJECTION 03 Accumulator Tank Levele e See Deviation No. 10 in Appendia 7A.
D4 Accumulator Tank Pressures e See Deviation No. 11 in Appendia 7A.
4 w
i i
TABLE 7.5-1 -
(Sheet 12 of 36)
e e-DISPLAY R C. 1.97 R.G. 1.97 MCR ITEM RECOMMINDE D DESIGN ACTUAL POWER TREND TSC, EDF NUMBER VARIABLE / SENSOR RANGE CATECORY RANGE RE0040_ANCY SUPPLY VARIABLE INDICATION COMPUTER 04A Accumulator Vent - - Open/ Closed N/A Vital Valve Position DC SI-ZS-2475 CS-2475-1 -
D7361
-SI-ZS-2476 CS-2476 - D7362 SI-ZS-2482 CS-2482-1 -
07364 SI-ZS-2483 CS-2483 - D7365 SI-ZS-2477 CS-2477-1 - 07366 SI-ZS-2486 CS-2486 - D7367 SI-ZS-2495 CS-2495-1 -
D7369 SI-ZS-2496 CS-2496 -
07369
- D5 Accumulator Isolation Closed or open 2 Open/ Closed N/A Vital valve Position Open/ Closed UPS SI-ZS-2403-1 Open/ Closed ZL-2403-1 - -
SI-ZS-2413-1 Open/ Closed ZL-2413-1 - -
SI-ZS-2423-1 ZL-2423-1 - -
SI-ZS-2433-1 ZL-2433-1 - -
D6 Boric Acid Charging 0 to 110% design 2 0-150 gpm N/A Vital Flow (0 to 85 spm) UPS CS-FT-183 FI-1934 - -
(Emergency Boration Flow).
D7 Flow in HPI System 0 to 110% design 2 0-800 gpm N/A 1 SI-FT-918 (0 to 605 gpe) Vital FI-918 - A0512 SI-FT-922 UPS FI-922 -
A05 4 SI-FT-937 (CS pump) -(0 to 715 spm) 0-1000 gpa FI-917 -
A0510 DO Flow in LPI System 0 to 110% design 2 See D1 09 Refueling Water Top to botton 2 See A6 Storage Tank Level ,
_RCS DIO Reactor Coolant Pump Motor current 3 0-400 amps N/A N/A Status RC-AP4-73OO (330 FLA) APS-7300 - -
RC-AfS-7304 AfS-7304 - -
RC-APS-7306 W 7306 - -
RC-Art-7 308 Art-7308 - -
TABLE 7.4-1 (Sheet 13 of 36)
o e
- S8 ITEM DESIGN ENVIRONMENTAL SEISMIC NUMBER VARIA8tE CATE CORY QUALIFICATION QUAL. OA TRENDING REMAM S/ NOTES D4A Accumulator Vent 2 Yes N/A Yes N/A
- Valve Position-D5 Accumulator Isolation 2 Yes N/A Yes N/A Valve Position D6 Boric Acid Charging 2 Yes N/A Yes N/A Flow D7 -Flow in HPI System 2 Yes N/A .Yes N/A DS Flow in LPI System See D1 D9 Refueling Water Storage See A6 Tank Level
' RCg D10 Reactor Coolant Pump 3 N/A N/A Yes N/A Status i
4
(
E T ABL E 7. 5-1 (Sheet 14 of 36)
~ .. . .. . . . _ . _ - - - - _ .. - ...
e *-
- DISPLAY R.C. 1.97 R.G. 1.97 MCR IlfM RECOMMENDED DESIGN ACTUAL POWE R TRE ND .TSC, EDF
. NUMBER VARIA8tE/ SENSOR RANCE CATEGORY RANGE REDUNDANCY SUPPLY VARIABLE INDICATION ~ COMPUTER 011 Primary System Safety Closed-not closed 2 Closed-Not N/A Relief Valve Positions closed (including PORV and code safety valves)
RC-PCV-456A Vital CS-456-Al - D-4495 RC-PCV-4569 DC CS-456-81 - D-4496 VB-YE-6032-1 Emerg YM-6032-1 -
V8-YE-6032-2 MCC YM-6832-2 -
D-5751 012 Pressurizer' Level Top to bottom 1 See A5 013 Pressurizer Heater Electric current 2 0-480 kW N/A N/A - - A0386 Status, Power Monitor 40307 A0300 A0309 014 Pressurizer Relief Top to botton 3 0-100" W.C. N/A N/A Tank (Quench Tank)
Level RC-LT-470' LI-470- -
40347 D15 Pressurizer Relief 50 F to 750 0F 3 50-250 0FM N/A N/A Tank (Quench Tank)
Temperature RC-TE-468 TI-468 -
A0376 D16 Pressurizer Relief 0 to design pressure 3 0-100 psig N/A N/A Tank (Quench Tank)
Pressure RC-PT-469 (0-100 psig) PI-469 -
A0340 SECONDARY D17 Steam Generator Level From tube sheet to 1 See A4 separators Die Steam Generator From atmospheric -2 See A2 Pressure pressure to 20%
above the lowest safety valve setting (1425 psig)
TABLE 7.5-1 (Sheet 15 of 36)
e -e*
SB ITEM DESIGN ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY QUALIFICATION QUAL. QA TREN0!NG REMARMS/ NOTES e
Ell Primary System Safety 2 Yes Yes Yes N/A Stem-mounted limit switches provide position Relief Valve Positions indication for the PORVs. Acoustic Monitoring (including PORV and System Monitors status of both the PORVs and . ,,
code safety walves) the safeties.
E12 Pressurizer Level 'See A5 ..
Pressurizer Heater Status, 3e N/A N/A Yes N/A # See Deviation No. 24 in Appendia 7A.
E13 Power Monitor .
014 Pressurizer Reaief Tank 3 N/A N/A Yes N/A (Quench Tank) Level. ,
N/A N/A Yes N/A # See Deviation No. 12 in Appendia 7A.
015 .Pressuriter Relief Tank 3 '
(Quench Tank) Temperature ,,
016 . Pressurizer Relief Tank 3 N/A N/A Yes N/A (Quench Tank) Pressure ,
SEC0h0ARY s
E17 Steam Generator Level See A4 DIR Steam Generator See A2 ,
Pressure o
be W
. 4
')
TABLE 7.5-1 (Sheet 16 of 36)
. e.
DISPLAY R.G. 1.97 R.C. 1.9/ MCR ITEM RECormENDED DESIGN ACTUAL POWER TREND TSC, EOF NUMBER VARIA8LE/ SENSOR RANGE CATECORY RANGE REDUNDANCY SUPPLY VARIA8LE INDICATION COMPUT E R D19 Safety-Relief Valve Closed-not closed 2 Closed-not N/A Emerg Position or Main closed MCC Steam Flow V8-YE-6820 (SG #4) YM-6020 - D5788 V8-YE-6821 (SG #3) YM-6021 -
WB-YE-6022 (SG #2) YM-6822 -
v8-YE-6e23 (SG #1) YM-6s23 -
D20 Main Feedwater Flow 0 to 110% design 3 0-Sn10 6 Lb/hr N/A N/A FW-FT-510 (SG #1) flow per SG FI-5104 FR-510 A0728 FW-F T-520 (SG #2) (0-4.2 a 106 lb/hr) FI-520A FR-520 A0738 FW-5T-530 (SG #3) FI-530A FR-530 A0740 FW-FT-540 (SG #4) FI-5404 FR-540 A0718 EMERGENCY FEEDWATER 021 Auxiliary or Emergency 0 to !!OE design 2 0-500 gpa N/A Vital reedwater Flow flow UPS FM-FT-4214-2 (SG #1) (O to 390 gpm) FI-4214-2 FR-4214 A0795 FW-FT-4224-2 (SG #2) FI-4234-2 F2-4214 A0796 FW-FT-4234-2 (SG #3) FI-4244-2 FR-4224 A0797 FW-FT-4244-2 (SG #4) FI-4224-2 FR-4224 A079e D22 Condensate Storage Plant specific Tank Water Level (0-40 ft)
FW-PT-4252 1 0-40 FT Yes Vital PI-4252 -
A0704 FW-PT-4257 UPS PI-4257 -
A0706 CONTAINPENT COOLING D23 Containment Spray Flow 0 to 110% design 2 flow (3400 gpm)
Containment Spray 0-60 psig# N/A Non-Pump Swction Vital Pressure UPS CBS-PT-2312 PI-2312 -
A0922 CBS-PT-2314 PI-2314 -
A0924 Containment Spray 0-500 psig# N/A Non-Pump Dischange Vital Pressure UPS CBS-PT-2313 PI-2313 -
A0923 CBS-PT-2315 PI-2315 - A0925 024 Heat Removal by the Plant-specific 2 Containment Fan Heat Removal System #
TABLE 7.5-1 (Sheet 17 of 36)
e e.
SB ITEM DESIGN ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY QUALIFICATION gJAL. QA TRENDING REMARMS/WOTES 019 Safety-Relief valve 2 Yes N/A Yes N/A Acoustic Monitoring System monitors position Position or Main of the SG safeties.
Steam Flow D20 Mein Feedwater Flow 3 N/A N/A Yes N/A EMERGENCV FEEDWATER D21 Ausiliary or Emergency 2 Yes N/A Yes N/A Feedwater Flow D22 Condensate Storage Tank 1 Yes Yes .Yes N/A Quallfled indication of condensate storage tank Water Level level is provided by the EFW pump suction pressure indication. A correlation between suction pressure indication and CST level for both pump running and not running situations will be provided for the operating crew. This correlation will be easily accessible when reading the suction pressure indication. The use of this instrumentation will be addressed in the operator training program.
CONTAINFENT Cn0 LING D23 Containment Spray Flow 2 Yes N/A Yes N/A e See Deviation No. 13 in Appendis 7A.
Containment Spray Pump Suction Pressure Containment Spray 2 Yes N/A Yes N/A Pump Discharge Pressure I
i D24 Heat Removal by the e See Deviation No. 25 in Appendia 7A.
Containment Fan Heat Removal Systeme ,
TABLE 7.5.-l (Sheet 14 of 36)
e e-DISPLAY R.G. 1.97 R.G. 1.97 MCR ITEM RECOMME NDED DESIGN ACTUAL POWER TRE ND TSC, EOF -
NUMBER VARIA8tE/ SENSOR RANCE CATEGORY RANGE REDUNDANCY SUPPLY VARIA8LE INDICATION COMPUTER D25 Containment Atmosphere 400 F to 400 0F 2 50-420 0FN N/A Vital Temperature UPS RC-TE-1313 RC-MM-7315 - Available through data link.
026 containment Sump w ter 50*F to 250 F0 2 Temperaturee CHEMICAL AND VOLUME CONTROL 027 Makeup Flow-in 0 to 110% design 2 0-200 gpm N/A N/A CS-FT-121 flow (150 gpm) FI-121A -
A0622 D20 Letdown Flow-out 0 to 110% design 2 0-200 gpm N/A N/A CS-FT-132 flow (135 gpm) FI-132 -
A0620 D29 Volume Control Tank Top to botton 2 0-00"# N/A N/A Level (141")
CS-LT-105 LI-105 LR-105 -
CS-LT-112 LI-112 - A0624 COOLING WATER D30 Component Cooling 400 F to 2000 F 2 0-175 0FN N/A Vital h ter Temperature to UPS ESF CC-TE-2171 TI-2171-1 -
A0271 ESF CC-TE-2271 TI-2271-1 -
A0269 1
D31 Component Cooling Water 0 to 110% design 2 0-13,000 gym N/A Non-Flow to ESF System flow (11,500 gpm) Vital CC-FT-2103 UPS FI-2103 -
A0273 CC-FT-2203 FI-2203 - A0272 03ta RHR and CBS l4est Enchanger PCOd Outlet ,
Valves CC-V266 - - Closed /Open N/A Emerg. CS-2245 -
D7023 CC-V272 NCC CS-2244 -
D7824 CC-V137 CS-2145 - D7021 CC-V145 CS-2144 -
D7022 D32 Cooling Tower Sump - -
0-60 FT N/A Vital Level UPS Su-L-6129 LI-6129 LR-6129 A1537 EW-L-6139 LI-6139 - -
1AOLE 7.5-1 (Sheet 19 of 36)
SB .
ITEM DESIGN ENVIRONMENTAL SEleAIC NUMBE R VARIA8LE CATE GORY QUALIFICATION QUAL. 9A TRINDING REMARNS/ NOTES D25 Containment Atmosphere 2 Yes N/A Yes N/A # See Deviation No. 14 in Appendia 7A.
Temperature D26 Containment Sump Water # See Deviation No. 15 in Appendia 74.
Temperature #
CHEMICAL AND VOLUME CONTROL 027 Ikkeup Flow-In 3e N/A N/A Yes N/A # See Deviation No. 16 in Appendix 7A.
D20 Letdown Flo d t 3# N/A N/A Yes N/A d See Deviation No. 17 in Appendia 7A.
029 volume Control Tank 3# N/A N/A Yes N/A # See. Deviation No. It in Appendia 7A.
Level COOLING WATER D30 Component Cooling Water 2 Yes N/A Yes N/A # See Deviation No. 19 in Appendia 7A.
Temperature to ESF D31 Component Cooling Water 2 Yes N/A Yes N/A Flow to ESF System D31a RHR and CSS Heat 2 Yes N/A Yes N/A E4chasnger PCCW Outlet Valves D32 Cooling Tower Sump 2 Yes N/A Yes N/A-Level TABLE 7.5-1 (Sheet 20 of 36)
- . ~ . - _ . - _. . -- . - _ . . , . . ._. .- .
e e I
! DISPLAY l R.G. 1.97 R.G. 1.97 MdR l Ji[M ' RECorWW NDED DESIGN ACTUAL POWER 1 REND TSC, EOF WUMBER VARI ABL E/SENSo# RANGE CATECORY RANGE RfDt MANCY SUPPLY VARIABLE INDICATION COMPUTER ,
D32a Service Water Flow - - G-2500 gpm N/A .Non- ,
to DG Heat Enchanger Vital SW FT-6101 UPS FI-6101 - -
Ste-F T-6191 Vital FI-6191 - -
.UPS D32b Cooling Tower Pump - -
0-150'F N/A Non-Discharge Temperature vital Ste-TE-6104 UPS TI-6104 -
A1503 SWTE-6194 TI-6194 - A1505 RADWASTE D33 Hig4 Level Radioactive Top to bottom 3 0-14 FTN N/A ' N/A Liquid (Floor Drain) (18 feet)
Tank Level WL-8.T-1462 (TK-59A) LI-1462 -
A1295 WL-LT-1466 (TK-598) LI-1466 - - i 034 Radioactive Gas Holdup O to 150E design 3 Tank Pressure" pressure VENT!tATION 035 Emergency Ventilation Open-closed status 2 Closed-Not N/A Vital ZL-537@3 - -
Damper Position Closed UPS ZL-5371-3 - -
PAH-OP-3*A ZL-5370-4 - -
PAH-OP-358 ZL-5371-4 - -
PArt-OP-36A ZL-5700-2 - -
PAH-OP-368 ZL-5704-2 - -
EAH-OP-304 2L-5630-2 -
D5142 EAH-OP-308 ZL-5631-2 - D5147 CAH-OP-34A ZL-5634 -
D5140 CA6H)P-348 ZL-5635 -
D5149 CAH-DP-34C Emerg. CS-5331 - -
CAH-OP-340 MCC CS-5329 - -
CBA-DP-534 - -
CBA-OP-538 - -
035a Fan Status: Control - - Running / N/A Emerg, CS-5328 -
D7034 Room Nkeup Air Fans Not Running MCC CS-5330 - D7035 CBA-FE-27A CBA-FN-278 b
TABLE 7.5-1 (Sheet 21 of 36)
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DISPLAY 1 R.G. 1.97 R.G. 1.97 MCR l ITEM RECDPmENDED DESIGN ACTUAL POWER TREND TSC, EOF l
- NUMBER VARI ABLE/ SENSOR RANCE CATEGORY RAACE RED M ANCY SUPPLY VAR LABLE INDICATION COMPUTER 1
.i
- D35b Contairument Enclosure - -
50-250*F N/A Wital RC-MM-7315 - Available through Data l Temperature UPS Link )
fTS-TE-10024 l FTS-TE-10028 D35c Primary Aunillary - -
50-250*F N/A Vital D NN-7315 - Available through Data i Building Temperature UPS Link l FTS-TE-1003 A FTS-1E-10038 D15d Diesel Generator - -
0-2000F N/A Won-Building Temperature Vital DAH-TE-5608 UPS TI-5688 - -
DAH-TE-5689 TI-5609 )
l D15e Service teater - -
0-1400F# N/A N/A - -
D6975 Pumphouse Temperature - -
D6977 SWA-TSPL 5612 06979 SW&TSHL 5600 SW&TSHL 5609 D15f Cooling Tower - - 0-140'F# N/A N/A - -
06993 Switchgear Area - -
D6909 Teeperature D6991 SW &TSHL 5699
, SWA-TSHL 5693 SW&TSHL $696 D35g Emergency Feedwater - -
0-140*F# N/A N/A - -
07900 Pumphouse Temperature EPA-TS84-5434 l
l 035h Cor. trol Sullding - -
300 -1100F# N/A N/A - -
D7023 l
Temperature - -
D7022
! CBA-TSHL-5190 - -
07026 C84-TSHL-5181 - -
D7027 i CBA-TSHL-5102 - -
D7028 CDA-TSHL-5580 1 CBA-TSHL-5581 0351 Containment Enclosure - - 0-2500 scfm W/A Non-Emergency Enhaust Fan Vital Discharge Flow UPS EAH-f1T-5791 FR-5791 FR-5791 A3777 i
TABLE 7,5-1 (Sheet 23 of 36)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . .A
- -. - . . . . - -. . ~ .~ _.-
. , , ~ . . -. ._.- - . - _. . . . . . . - - - . .- - . . . . . .- . . ..
t l . e.
l l
! SS ITEM DESIGI [NVIRONMENTAL SFISMIC NUMBER WARIABLE CATEGORY QUAL IFICATION QUAL. QA TRfhDING REMARKS / NOTES D35b Containsent Enclosure 2 Yes N/A Yes N/A Temperature D35c Primary Auxiliary Building 2 Yes N/A Yes N/A Temperature 035d Diesel Generator Building 2 Yes N/A Yes N/A Temperature t
l D35e Service Water pumphouse 2 Yes N/A Yes N/A eHigh Temperature alare provided Temperature Setpoint; 104 0 F l
l 035F Cooling Tower Switchgear 2 Yes N/A Yes N/A #High Temperature alare provided Area Temperature Setpoint: 1040F-035g Emergency Feedwater 2 Yes N/A Yes- Yes #High Temperature alare provided Pumphouse Temperature Setpoint: 1100F 035h Control Sullding 2 Yes N/A Yes Yes #High Temperature alare provided Temperature Setpoints: 5180, Slet, 5182 - 1100F 5580, 5501 - 950F 0351 Containment Enclosure 2 Tes N/A Yes N/A ,
Emenpency Enhaust Fan Discharge Flow l
l l
l l
! TA8LE 7.5-1 (Sheet 24 of 36) l l _ _
e e.
e-DISPL AY ,,
R.C. 1.97 R.G. 1.97 MCR ITEM REC 0pm1NDED DESIGN AC10AL POWER TREND TSC. EOF NUMSER VARIASLE/ SENSOR RANCE CATEGORY RANGE REDUNDANCY SUPPLY VARIA8tE INDICATION COMPUTER ,
POWER SUPPL 3ES ,,, .
q D36 Status of Standby Posser , .
4160 Emergency Bus Plant-specific 2 0-5000 V N/A N/A Availability EDC-VT R-970s VP4-9708 - A2306 EDE-VTR-9718 VFS-9718 -
A2309 400 Emergency Bus Plant-sf.ecific 2 0-600 V N/A N/A Availability EDE-VIR-9784 VTR-9784 - -
EDE-VTR-97e5 VTR-9785 - -
125 V DC Plant-specific 2 0-150 V dc N/A Vital EO-VTR-9750 UPS VPS-9750 - A2052 ED-VTR-97S2 VPS-9752 - A2055 ED-VTR-9754 VPS-9754 -
A2050 ED-VTR-9756 Vet-9756 -
A2061 120 W AC Vital Bus Plant-specific 2 0-150 V N/A N/A - -
A1016 voltage A1817 Vital Bus 1A N/A - -
A1818 Vital Bus 18 A1019 Vital Bus 1C N/A - - A1820 Vital Bus 10 A1821 Vital Sus IE N/A - -
Vital Sus IF N/A - -
N/A - -
Emergency Diesel Plant-specific 2 VM O-5000 V N/A Emerg.
Generator FM 55-65 HE MCC AM O-2000 amp '
EDE-VTR-9700-1 (DG A) VPS-9 700-1 MR-9700A A 2712 EDE47R-9700-3 6M O-9000 MW FPS-9 700-3 MR-97008 A 2713 EDE-ATR-9700-1 APS-9 700-1 MR-97004 A 2714 EDE-WTR-9700-3 6ft-9700-3 MR-97008 A 2715 EDE-VTR-9710-1 (DG 9) VPS-9 710-1 MR-9710A A 2732 EDE4TR-9710-3 F PS-9 710-3 MR-97108 A 2733 EDE-ATR-9710-1 Af5-9 710-1 MR-9710A A 2734 EDE-WTR-9710-3 6e9-9710-3 MR-97108 A 2735 w
em TABLE 7.5-1 (Sheet 25 of 36)
.. _ . . . - . - - . , ,_ .. _- ..~
_ .. ---.-~_-.-a-..- ,_ - . . - . .-
.g
- t SS
! Iff R DESIGN ENVIROGN NTAL SEISMIC
.MR WARIASLE CATEODRY QUALIr!CA110h QUAL. QA TRENDING REMARNS/ NOTES P0hER SUPPLIES 016 Status of Standby Penser 4160 Emergency Bus 2 Yes N/A Yes N/A Availability 400 Emergency Dus 2 Yes N/A Yes N/A Availability ,
125 V DC 2 Yes N/A Yes N/A-120 V AC 2 -Yes N/A Yes N/A Emergency Diesel 2 Yes N/A Yes N/A Generator s
r r .. ;
I l I l
f l
TASLE 7.5-3 (Sheet 26 of 36)
e . a .
DISPL'Y -
R.G. 1.97 R.G. 1.97 MCR REC 0rWWNDED DESIGN ACTUAL POWE R TREmo TSC, EOF ITEM suMBE R VARIABLE /SEWSOR RANGE CATECORY RANGE REDUNDANCY SUPPLY VARIABLE INDICATION COMPUTER OMRUSTISLE GAS CDWTROL D37 Hydrogen Recombiner: - - 0-2000 0 f N/A Emerg.
Temperature MCC CGC-TE-2703A. S C TI-2703 -- -
CGC-TE-27064, 3, C TI-2706 - -
TYPE E WARIASLES. RELEASE ASSES COSTAISPENT RADIATION El Containment Area 1 R/hr to 107 R/hr 1 1 to 10 8 Yes Vital Available Radiation R/hr UPS Through Art-RC-6576 A RN-65764 RR-65764 Data Link Art-RC-6576 8 RN-65768 RR-65768 AREA RA0!ATION E2 ' Radiation Esposure Rate 10~1 R/hr to 104 3 10-2 to N/A N/A .
Available (Inside buildings or R/hr 104 R/hr Br9- M 599 Art-NFS-6599 Through Data areas where access is Link required to service equipment important to safety)
Wrt-R-6508-1, -2 (PAS High Range)
Art-R-6563-1, -2 (PAS High Range)
RPS-R-6517-1, -2 (RHR pump Vault 1&2 High Range)
Arg-R-6518 (Spent Fuel High Range)
WOSLE CASES E3 Containment or Punse 10-6 uCi/cc to 2 See E7 Effluent 105 uCi/cc (not needed if effluent discharges through common plant vent)
O to 110E flou E4 Reactor Shield 10-6 uCi/cc to 2 See E7 Suilding Annulus 80' uCi/cc (not .
needed if effluent discharges through common plant vent)
O to 110E flow TABLE 7.%-1 (Sheet 27 of 36)
o
- O .
S8 Ilf M DESIGN ENVIRONMENTAL SFISMIC NURSER VARIABLE CATEGORY QUALIFICATION QUAL. QA TRENDING REMARNS/ NOTES COMBUSTIBLE GAS CONTROL D37 Hydrogen Recombiner: 2 Yes N/A Yes N/A Temperature TYPE E WARIASLES. RELIASE ASSESSMENT
_CONTAllrIENT RADIATION El Containment Area 1 Yes Yes Yes Yes Radiation ARE A RADI ATION E2 Radiation Esposure Rate 3 N/A N/A Yes N/A The high-range monitors have been installed to (inside buildings or monitor the entrances to the PA8 and RHR pump areas where access is vault. The spent fuel pool area is also required to service monitored with a high-range detector. Individual equipment important to cubicles are not monitored. Portable instruments safety) will be used for entry into high radiation areas (real or suspected).
NOSLE GASES E3 Containment or Purge See E7 Discharge through plant vent stack.
Effluent E4 Reactor Shield Sullding See ET Discharges through plant vent stack.
Annulus l
r TA8LE 7.%I (Sheet 28 of 36)
s
- e .
DISPLAY R.G. 1.97 R.G. 1.97 RCR ITEM RECOrWTMDED DESIGN ACTUAL PohdIR TREND TSC, EOF SURSE R VAR! ASLE/SEWSOR RANGE CATICORY RANGE DEDOWOANCY SUPPt.Y VARIAOLE 140ICATION COMPUTER E5 Awaillary Building 10-0 uCi/cc to 2 See E7 (including any building 10 3 uCi/cc containing primary (not needed if systee gases, e.g., ef fluent dis-anaste gas decay tank) charges through common plant went)
O to 110% flome E6 Condenser Air Removal 104 uCi/cc to 2 See [7 System Enhaust 10% uCi/cc (not needed if effluent discharges through c m plant went!
O to 11CE flone E7 em Plant Vent or N/A Emers. Available Phltipurpose vent 10~0 uCi/cc to 2 10~# to MCC RR-6520-1 Through Discharging Any of 104 uCi/cc IOS uC1/cc h-6528 RR-6528-2 Data Link Above Releases (if Rf4-Mrt-6599 containment purge is 0 to 110% flone 2 0 to 3,6 s included) (0 to 2 a 105 scfa) 105 scfm Art-RE-6528-1. -2, -3 Ars-f T-6577 ES Vent free Steam 10-I uCi/cc to 2 1 to 2/A Emerg. Available Generator Safety 103 uCi/cc 10% ar/hr# MCC RfS-MPl-6599 Arv-Nrt-6599 Through Belief Valves or (Duration of releases Data Link Atmospheric Dump Values in seconds and mass Rf9-RE-6481-1,21 of steam per unit 6402-1,2 time) -
Safety / Relief valve See D19 Position YE-6820 YE-6021
- YE-4822 YE-6023 E9 All Other Identified Plant Release Points #
1 TA8tt 7.5-1 (Sheet 29 of 36)
_ _ _ _ _ _._.. . _. ,_ - - - _ _ ._ -. - -- - - m--- - - - - - - - -
l . % e .
Se l ITEM DE SIGN INVIRONME NT AL SEISMIC I NungER WARI & E CATEGORY OUAL IFICATION QUAT. . TRENDING 9A REMARNS/ NOTES WOStE CASES ES Auniliary Building See E7 Discharges through plant went stack.
(including any building containing primary i systeesgases, e.g.,
l .maaste gas Jecay tank)
E6 Condenser Air Removal See E7 Dischenpes through plant went stack.
System Enhaust l E7 cm Plant Vent or 2 Yes N/A Yes Yes I rkltipurpose Vent Flow element provides a signal to the radiation Dischaqing Any of monitors to permit the radiation monitors to above Releases (if calculate the microcuries per cubic centimeter containment punge is flouing in the duct and microcuries per second included) released through the plant went stack.
Ee vent from Steam Generator 2 Yes N/A Yes Yes safety Relief valves #
Correlation from er/hr to uci/cc is included or Atmospheric Dump in the procedure for off-site dose Valves assessment. Direct readout in ucl/cc is not required to support this procedure.
The safety / relief walve position monitors can be used to determine the existence of flow through these valves.
E9 All other Identified Plant a None Identified.
Delease Points
- TA8tE 7.5-1 (Sheet 30 of 36)
r e 4 e.
+
l DISPLAY
! R.C, 1.97 R.G. 1.97 MCR_
RECXNMENDED DE SIGN ACTUAL POWER TREND TSC, EOF IllM CAiiOORY RANCE SUPPLY VARIARLE IND1 CATION COMPUT[R NuretR VARIASLE/ SENSOR RANGE R(DUND_ANCY t
l PARTICUL ATES AND HALOGENS
[10 All Identified Plant 10'3 uCi/cc to 3 <10-3 uCi/cc N/A N/A N/A N/A N/A Release Points (ascept 102 uC1/cc to s102 uCi/cc steam generator safety relief valves or atmospheric steam dump l valves and condenser air removal systen l
l enhaust). Sampling 0 to 110% flow 0 to 3.6 a N/A N/A h h 6599 - Available 10 5 scfm Through
! with On-site Analysis (0 to 2 a 10 5 scfm Data Link
! Capability.
l RNSMD-53-2 E12 Airborne Radiohalogens 10-' uCi/cc to 3 (10-9 uCi/cc N/A N/A N/A - -
! and Particulates 10-3 uC1/cc to s10-3 (portable sampling uCi/cc with on-site analysis capability)
Air Samplers:
Low Volume High Volume l Personnel l
Continuous Air F%nitor I E13 Plant and Environs 10~3 R/Hr to 3 0-1 R/Hr N/A N/A N/A N/A N/A
( Sadiation (portable 104 R/Hr photons beta / gamma instrumentation) 10-3 reds /hr to 0-1,000 R/Hr N/A N/A N/A N/A
! Ion Chamber 104 reds /hr, beta gamma (Low Range) radiations and low- Up to 10,000 N/A N/A N/A N/A Ion Chamber energy photons R/Hr gamma (Mid Range) 0-50,000 CPM N/A N/A N/A N/A
! Ion Chamber beta / gamma (High Range) O-200 MR/Hr N/A N/A N/A N/A Ceiger f%eller beta / gamma Detestor 0-500,000 CPM N/A N/A N/A N/A Geiger Mueller alpha l
l Detector 0.001-10 R/Hr N/A N/A N/A N/A Alpha Scintillation neutron Telewsetector Rate Detector E14 Plant and Environs (Isotopic analysis) 3 Multichannel N/A N/A N/A N/A N/A Radioactivity 9may (portable spectrometer instrumentation)
TARLE 7.S-1 j (Sheet 31 of 36)
.. _ _ . . . . _ . . - . . . . . . ._ _. _._. _ _ , - _ . ~ . . . _ _ . . , _ . _ _ ___
e' 4 e.
SS ITEM DESIGIB ENWIHOAPENT AL SEISMIC NURRER WARIASLE CATEGORY QUALIFICATION Qual. On TREIIDING REPtARMS/ NOTES PARTICUL ATES AW HALOGENS l Elo All Identified Plant 3 N/A N/A Yes N/A l Release Points (eacept steam generator safety relief valves or atmospheric steam dune valves and condenser J l air removal system l
enhaust), Sampline with on-Site Analysis capability l
l El2 Airborne Radiohalogens 3 N/A N/A Yes N/A and Particulates (port-able sampling with on-site analysis capability) l El3 Plant and Environs 3 N/A N/A Yes N/A Radiation (portable instrumentation)
Ett Plant and Environs Radio- 3 N/A N/A. Yes N/A Function provided by gamma spectroscopy system activity (portable located in the Counting Room. Portable air instrumentation) sampler used to obtain the air samples.
l TAetE 7.5-1 (Sheet 32 of 36)'
.-~ . . . - _ . - . _ _ _ _ _ . - ._. .-- .-
. i e.
I DISPLAY R.C. 1.97 R.G. 1.97 MCA ITEM RECormf MDED DE SIGN ACTUAL p0WER TRE ND TSC, EOF WR WARIASLE/ SENSOR RANCE CATEGORY RANCE REDUNOANCY SUPPLY WARIABLE INDICATION COHPUTER l
METEORotOGY l
I EIS Wind Direction 0 to 360* (15' 3 0-540*e N/A N/A Computer Computer A1630
! 43 feet accuracy with a Accuracy: 13.20 A1627 209 feet deflection of 10 0), Threshold: 0.5 mph Starting speed less Damping Rates: 0.4 l than 0.4 aps (1.0 mph) Distance Constant:
Damping ratio greater 1.5 meters-than or equal to 0.4 delay distance less l than or equal to 2 meters.
Ele Wind Speed 0 to 22 aps (50 mph) 3 0-100 mph N/A N/A Computer Computer A1620 l 43 feet 10.2 aps (0.5 mph) Accuracy: to.32 mph A1626 i 209 feet accuracy for speeds @ 5 mph less than 2 aps (5 mph), 10.57 mph ICE for speeds in escess 9 50 mph ,'
of 2 mas (5 mph). with a Threshold: 0.5 mph starting threshold of less Distance Constant than 0.4 aps (1.0 mph) 1,5 meters and a distance constant not to encoed 2 meters.
E17 Estimation of Based on vertical 3 Temperature Atmospheric Stability temperature -300 to 1100 F N/A N/A Computer Computer A1632 43 feet (temp) . difference from Delta T A1631 43-150 feet (delta-T) primary meteorological -100 F to it'F 43-209 feet (delta-T) system, -50 C to ' Accuracy: 10.12*F 100 C (-90 F to aso r) and 0.150C accurary per 50--meter intervals (10.3 0F accuracy per 164-foot intervals) o~r analogous range for alternative stability estimate, TA8tE 7.5-1 (Sheet 33 of 36)
.. __. . ,__....m _ _ _ . .
_ _.m . . . . . . _ . . . . . _ . _ .._...m. _. . . - . _ , . ._
. 1, c, S8 ..
ITEM DESIGN ENVIRONMENTAL SF~.SMIC muMBER VARIASLE CATEG0eV QUALIFICATION guAL. OA TRENDING REMAtttS/40TES r
PETE000 LOGY EIS Wind Direction *.
3 N/A N/A Yes Yes Communication with the National Weather ,
service is available by telephone.
e mange of 0-540' selected to minimize .
recorder pen travel for northerly wind directions.
Ett Wind Speed 3 N/A N/A Yes Yes P - nication with the National Weather Service is available by telephone E17 Estimation of Atmospheric 3 N/A N/A Yes Yes Communication with the National Weather Stability Service is available by telephone s
.. 2 e
9 TABLE 7.% 1 *
(Sheet 34 of 36)
- _. . . . . - . . . - . . . . ~ . .- . _ - .. ... - - ..
- . s o.
1 DISPLAY R.C. 1.97 R.C. 1.97 MCR ITEM SEcormENDED DESIGN ACTUAL POWER TetNo TSC, EOF NunSER VARIA8tE/SENSo# RANGE CATEGORY RAssGE '#EDundDANCY SUPPLY VAe!'?tE INDICATION COMPUTER AEIDENT SMPLING CAPASILITY ,
l EIS Primery Coolant and . Grab sample 3 - N/A N/A N/A N/A N/A Sump l Gross Activity I uCi/ml to I uCi/ml to
( 10 Ci/el to ci/al
- Gamma Spectrum (Isotopic Analysis) Isotopic analysis Doron Content 0 to 6000 ppe O to 6000 ppe Chloride Content 0 to 20 ppe O to 20 ppe Dissolved Hydrogen 0 to 2000CC (STP)/RG 0 to 2000CC
, (STP)/NG j Dissolved Onygen 0 to 20 ppe #
pH 1 to 13 1 to 13 Ett Containment Air Grab sample 3 -
4/A N/A N/A N/A N/A Hydrogen Content 0 to 101 0 to 105 Onygen Content 0 to 301 0 to 301 Gamma Spectrum (Isotopic analysis) Isotopic analysis M
e eb l
l TASLE 7. % 1 (Sheet 35 of 36)
L,.e'o.
-C 1
Se IffR DESIGN ENWIRONMENTAL SEISMIC NUMBER WARIASLE CATEGORY QUALIFICATION QUAL. QA TRfmDING REMARNS/ NOTES ACCIDENT SAMLING CARASILITY ,_
EIS Primary Coolant and Sump 3 ' N/A N/A Ves N/A # See Deviat'lon No '21'in Appendia 74, E19 Containment Air. 3 N/A N/A Ves N/A
, n.
4 J
~
k s -
?
5 t
T TABLE 7.'s-1 (Sheet 36 of 16)
- .. e *.%
g .m
. .. e ..
TABLE 7.5-2 l (Sheet 1 of 6) 48 CONTROL ROOM INDICATORS AND/OR RECORDERS AVA11.AgtE TO THE OPERATOR TO MDNITOR SIGNIFICANT Pt.AltT PARAhETERS DURINC NORMA 1 OPERATION INCLUDINC OPERAft0FAL OCCt1LENCES No. of Channele Indicated Indicator /
F*remeter Available Range Accuracy (I) Recorder Location Notes NUCLEAR IN$TEHENTATION
- 1. Source Range
- a. Count rate 2 1 to 10 counts /sec 117 of the Both channele control one two-pen recorder to Itnear full indicated. Either goerd used to record any of scale analog any be selected for the a nuclear channele voltage recording. (2 source range, 2 intermediate range and 4 power range) en
- b. Startup rate 2 0.5 to 5.0 decades / +7I of the m Both channels control en -
ein linear full indicated.
scale analog Board $ p.
voltage "
- 2. Intermediate Range .
- e. Current 2 10'II to 10" 1 7% of the goth channels Control linear full Indicated. Either goard scale analog may be selected voltage and for recording using 40 13% of the the recorder in item linear full I above.
scale voltage in the range ofgo-4 10~ amps to
- b. Startup rate 2 0.5 to 5.0 decadeel
- 17% of the Both chsnnele Control sin linear full indicated. Board scale analog t.
- g voltage c o
- 3. Power Range ,a o.
a
- a. Uncalibrated ion 4 wo chamber current
- 0 to 120% of full ~+1% of full All 8 current NIS rocks ,3 Power current power current signale indicated. in control e (top and bottom uncompenested room 8$
ion chambers)
TABLE 7.5-2 -
l (Sheet 2 of 6) ' **
No. of -
Channele Indicate parameter Avettsble Accuracy {g) Indicator /
Ray Recorder Location Notes
- b. Calibrated ton 4 0 to 125I of full chamber turrent power current 121 full All 8 current signale Control
_(top and botton power current recorded on four 2 pen Board (0 to sea) recorders).
uncoopensated ton chambers)
Recorder 1 - upper currents for two
. diagonally opposed detectore.
Recorder 2 - upper currente for remain-ing detectore.
Recorder 3 - lower currente for two diagonally opposed to detectors. .ns "
Recorder 4 - lower 88 **
currente for remain- $ o.
ing detectors.
- y
- c. Urper and lower 4 -60 to 601 lon chamber cur- ilt of full Dissonally opposed Control power channele may be rent difference Board selected for record-ing at the some time using recorder in Ites 1.
- d. Average flux of 4 0 to 120% of the top and tot- full power 13% of full All 4 channele indicat- Control power for ed. Any 2 of the four Board toe ton chamber indication (I full power) channele may be recorded 121 for veing recorder in Ites recording 1 above,
- e. Average flux ef 0 to 2001 of the top and bot-2 i23 of full Both channele recorded. Control full power power to toe ton chambers ~
1201 Board Ig (power rense
+61 of full yQ overpower) pcwer to 2001 8
m c6 Qg
- f. Flux dtfforence 4 -30 to 301 a of the top and 141 All 4 channele indicated. Control 5" bottoe ton Board to b
" C" chambere
. se ,
/, .,
. . ':t ,
O
. .. 1 i.
TABLE 7.5-2 l (Sheet 3 Of 6) 48 18 0 . of
~ Channelo Indicator /
P"remeter Available Range Indicatej Accuracy Itecorder Location 180 t ee
- 1. T 1/ loop 530' - 630 F 14 F All channele Control
( N I D Id) indicated. Board
- 2. AT 1/ loop 0 to 1501 of 14% of full All channelo indicated. Control (measured) '
full powerAT powerAT One channel to select- Board
- a. T or T ed for recording.
eold hot 1.T ,
0 m M'r -+41 47 channele are Control (sesoured. 1.T wide range) looholdper recNedon2-two Soard pen recorders. M g
4 T cel.I channele are l M record 45 on 2 - two 48 ""
pen recorders. b **
- 3. Overpower 6T 1/ loop Setpoint 0 to 1502 of ~+41 of full All channels indicated. Control
>J full power A T power A T one channel to selected Board for recording.
4 Overteeperature 1/ loop b to 150% of a T Setpoint 24% of full All channele indicated. Control full power a T power A T one channel to selected Board for recording.
- 5. Pressuriner 4 1700 to 2500 psts 228 poi All channele indicated.
Pressure Control Board
- 6. Preseuetter Level 3 Entire distance 13.51 AP All channelo indicated. Control between tape level at Two pen recorder used.
One channel to selected Board second pen records
- 2250 pela for recording reference level signal
- 1. Primary Coolant 3/Joop Flow 0 to 120% of Repeatability All channele indicated. 6 ;>
Control
- u rated flow of +4.5I of Soard ,
fall flow. ca
" 9"
- 1 1/ loop 0 to 400 ac amps M 4 Pimp Motor Current .
-+1.61 All channels indicated. Control One channel for each ,, f, Board pump e 9.'Systee Pressure 2 0 to 3000 psig w co Vide Range *1.8% All.channale indicated Control and recorded. Board
e TABLE 7.5-2 (Sheet 4 of 6) .. l s i.
43 No. of Channele P rameter Indicateg Indicator /
Availah Range Accuracy Recorder 1.ocation Notee
_ REACTOR CONTR01, SYSTEM
- 1. Rod Speed 1 5 to 75 stepeletn. +21 The one channel to control indicated. Board
- 2. Auctioneered 1 530 to 630'T 14 F The one channel to Control Any one of the T ave recorded. Board channeleintoth$'8 auctioneer may be bypassed
- 3. T
I'"" 1 530 to 630 F 14 F The one channel to Control recorded. Board M 4 Control Rod M*
Foottion If system not available. "~
borate and seaple e accordingly. y
- a. Number of steps 1/ group 0 to 230 steps of demanded rod 11 step Each group to indicated Control These signale are used withdrawal during rod motion. Board- in conjuction with the measured position signale (4b) to detect deviation of any individual rod from the demanded position. A deviation will actuate an alarm and annunciator.
- b. Full length I for each 0 to 228 stepe 14 stepa tach rod position rod seasured rod Control poettion indicated. Board
- 5. Control Rod 4 0 to 230 stepe 12.5% of total Bank Demanded All 4 control rod bank Control 1. One channel for yy Foottion bank travel positions are recorded Board along with the low-low each control bank. *B
- 2. An alora and annun- cn i limit alarm for each c1stor to,setuated *p bank.
when the last M e rod control bank E to be withdrawn reaches @
the withdrawat limit.
when any red control bank reaches the low insertion limit, and when acy rod control bank reaches the low-
, low insertion limit.
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TABLE 7.5-2 ' "
(Sheet 5 of 6) 46 No. of Chann,1s P'rameter Indicate Indicator /
Available Range Accuracy {g) Recorder Location Notes CONTAlWMENT SYSTgM
- 1. Containment Pressure
- 2 0 to 60 psig +1.8% All 4 channels 2 -5 to 160 psig Control indicated and 1 Board to recorded. 46
_FEEDWATER AND STEAM SYSTEMS
- 1. Energancy Feedveter 1/ feed 0 ta 200 gpa (later)
Flow line All channels Control indicated and Board One channel to esseure l l recorded, the flow to each stese 44 45 generator.
- 2. Stese Cenerator 3/stese O to 1001 Level (narrow generator 14% of AF All channele Control range) 'evel (hot) Indicated. The Board n,
channele used for ,, to control are re- en >-
corded. g*,,
- 3. Steam Cenerator 1/stese 0 to 1001 n Level (vide generator 15% of level All channels Control ranga) (cold) recorded. Board 4 Steae Cenerator level signal +7 to -3 feet ~
+4%
The one channel to indicated.
- 5. Main Feedwater 2/stene O to 5 X 10 lbs/hr +52 Flow All channele indicated.
generator Control The channele used for Board control are recorded.
- 6. Magnitude of 1/ main 0 to 100% of valve Signal controlling I/ bypass opening
~+1.51 All channele indicated. Control 1. One channel for each Main and typase . Board emin and , bypass feed-Feedwater Control water control valve Valves
- 2. OPEN/ CLOSED indication to provided in the L. g> 40 control room for each $e main and bypsea feed gg 7 Steen Flav 6 water control valve % g 2/stene O to 5 x 10 lbs/hr %C 4
~+5.51 All channele indicated. Control 3 generator Accuracy to equipment -- r, The channele used for Board espability; however, control are recorded, ll ,,
absolute accuracy de- La oo pende on applicant cali-bration against feedveter flow.
_ , , ,_ , _ _.. . ~ , - . - - - * * ~ ~ " "
TABLE 7.5-2
- l (Sheet 6 of 6) , .. de No. of Channelo Indicate Indicator /
P'rameter Available Range Accuracy {g). Recorder Location Notes
- 8. Stese Line 3/ loop 0 to 1300 peig All chonnele indicated . Control Pressure 141 end 1 to recorded. Board
- 9. Steen Dump I 0-1001 of steen The one channel to Demand 11.52 control OrtN/CLostD indication !
. dump valves open indicated. Board to provided in the 48 control room for each steam dump valve
- 10. Turbine Impulse 2 0 to 860 pels 13.51 Both channele Chamber Pressure control Ortw/CLostD indication l indicated. Board is provided in the 46 control room for each turbloe stop valve ja m
u >.
$$ e.
N e
kt s a C 3 (1) Inclades channel' accuracy and envirr-neentet ef fects e n.
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bd up
SBN-864 ATTACHMENT II (FSARAPPENDIX7A)
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- APPENDIX 7A Deviations and Justifications f
Appendix 7A contains a listing of all Accident Monitoring Instrumentation (AMI) variables that have deviations from the design criteria stated in Subsection 7.5.4.4 or the recommendations in Regulatory Guide 1.97. The " Data Table" headings in Appendix 7A refer to Table 7.5-1 items.
AMI variables not included in Appendix 7A have no deviations from the above criteria.
i i
O TABLE OF CONTENTS ,
Deviation Number Variable Page 1 SG Pressure................................................
2 Pressurizer Level..........................................
3 RWST Level.................................................
4 Containment Hydrogen Concentration.........................
5 RCS Soluble Boron Concentration............................
6 RCS Hot Leg Water Temperature..............................
7 RCS Cold Leg Water Temperature . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
8 Radiation Level in Circulating Primary Coolant.............
9 Effluent Radioactivity - Noble Cases (Inside buildings or areas where penetrations or hatches are located)...............................................
10 Accumulator Tank Level.....................................
11 Accumulator Tank Pressure..................................
12 Quench Tank Temperature....................................
13 Containment Spray Flow.....................................
14 Containment Atmosphere Temperature.........................
15 Containment Sump Water Temperature.........................
16 Makeup Flow-In.............................................
17 Letdown Flow-Out...........................................
18 Volume Control Tank Level.....-.............................
19 Component Cooling Water Temperature . . . . . . . . . . . . . . . . . . . . . . . .
20 High-Level Radioactive Liquid Tank Level....................
21 Discolved Oxygen in Primary Coolant (Grab sample)..............................................
22 RHR Heat Exchanger Outlet Temperature......................
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TABLE OF CONTENTS
. (Continued)
Deviation Number Variable Page 23 Containment Drainage Sump Water Level......................
24 Pressurizer Heater Status (Power Monitor) . . . . . . . . . . . . . . . . . .
25 Heat Removal by the Containment Fan Heat Removal System.....
26 Radioactive Gas Holdup Tank Pressure........................
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O SEABROOK STATION UNIT NO. 1 e
REGULATORY CUIDE 1.97, REVISICN 3 REVIEW Deviation No. 1 Data Table Variable Item No.
- Stenst Generator Pressure A2, D18 Deviation Frtm Regulatory Guide 1.97 Guidance The range deviates from the recommended range for Type D variable.
Actual range is 0-1300 psig, versus 0-1425 psig recommended (based on 20%
margin above lowest safety valve setpoint - 1185 psig).
Justification The range of the installed instruments extends beyond the lowest safety valve setting with a margin of approximately 10%. This range envelopes the highest safety valve setting (1255 psis). Therefore, the existing range is adequate to monitor the expected steam 6enerator pressures.
In addition to these instruments, nonqualified main steam pressure indication with a range of 0-1500 psig for each steam generator is available at the MCB. This envelopes the recommended range of 0-1425 psig. The transmitters are MS-PT-3001, 3002, 3003, 3004.
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7A-1 l
l SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97. REVISION 3 REVIEW Deviation No. 2 Data Table Variable Item No.
Pressurizer Level AS, D12 Deviation From Regulatory Guide 1.97 Guidance Actual range is 61.75"-581.25" above the bottom reference versus a recommended range from the bottom to the top.
Justification This range covers from approximately 10% to 94% of the pressurizer volume and is sufficient for the required monitoring function.
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t 7A-2
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 3 Data Table Variable Item No.
RWST Level A6 Deviation From Regulatory Guide 1.97 Guidance The actual range starts at 22,000 gallons versus the recommended range 4
starting at the bottom of the tank.
Justification The indicated range measures the usable volume of the RWST and is i adequate for the required monitoring function.
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SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 4 Data Table Variable Item No.
Containment Hydrogen Concentration A8 Deviation From Regulatory Guide 1.97 Guidance continuous indication is not provided since the hydrogen analyzer is normally isolated from the containment.
Justification The hydrogen analyzer is normally in the " Standby" mode to preclude a long warm-up time. The analyzer can be operational within 30 minutes of the initiation of an SI signal as required by NUREG-0737 Item II.F.1.
Since hydrogen buildup is a slow process and sufficient time is available to put the analyzer into operation, continuous indication is not required during power operation.
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SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 5 Data Table Variable Item No.
RCS Soluble Boron Concentration B3 Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
< Justification Under accident conditions, determination of boron concentration will be made by analysis of samples obtained via the post-accident sample panel.
Analysis capability is available to envelope the recommended range of 0-6000 ppm boron. The Seabrook-specific ERPs do not require that the operating crew monitor this variable with on-line instrumentation; therefore, it is not considered AMI.
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SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 6 Data Table Variable Item No.
RCS Hot Leg Water Temperature B5 Deviations From Regulatory Guide 1.97 Guidance All four channels (indication and recording) are powered from the same power supply.
Justification The hot les RTDs provide the primary temperature measurement for each hot leg. Diverse measurement is provided by the core exit thermocouples. The core exit thermocouples are redundant, thereby assuring the availability of this indication in the event UPS-I-1A is lost.
I 7A-6
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l SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 7 l Data Table Variable Item No.
RCS Cold Leg Water Temperature B4, B6 Deviation From Regulatory Guide 1.97 Guidance All channels (indication and recording) are powered from the same power supply.
Justification The cold leg RTDs provide the primary tempertture measurement for each cold leg. Diverse measurement is provided by the steam generator pressure channels. The Westinghouse Nuclear Steam Supply System is designed such that the cold les temperature approximates the saturation temperature corresponding to secondary pressure. It has been confirmed that there would be only a small variance between the actual cold leg temperature and the saturation temperature corresponding to steamline pressure during cooldown to cold shutdown. This correlation has been verified during actual plant operations.
The steam generator pressure channels (Item No. A2) are redundant, thereby assuring the availability of this indication in the event power to the cold les RTDs is lost.
- 1. I.etter from J. J. Sheppard, Westinghouse Owner's Group to D. G. Eisenhut, U.S. Nuclear Regulatory Commission, OG-94 (revised), dated June 14, 1983.
i 7A-7 l
SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 8 Data Table Variable Item No.
Radiation Level in Circulating C2
> Primary Coolant Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification The post-accident sampling system and analysis will be used to obtain measurements of the radiation levels in the primary coolant loops to satisfy ERP requirements. The Seabrook-specific ERPs do not require that the operating crew monitor this variable with on-line instrumentation; therefore, i it is not considered AMI.
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 9 Data Table Variable Item No.
Effluent Radioactivity - Noble cases C13 (Inside buildings or areas where penetrations or hatches are located.)
Deviation From Regulatory Guide 1.97 Guidance
~
The installed range, 10 to 10 CPM (corresponding to 6 x 10 to 10 uCi/cc), does not envelope the recommended range (10~ to 10 uCi/ce).
Justification The containment structure and all penetration / hatch areas are surrounded by the containment enclosure building. The exhaust from the containment enclosure building is monitored for gross activity. The containment enclosure building exhaust is routed to the main plant vent stack, where it is monitored (10~ - 10 uCi/cc) prior to discharge.
SEABROOK STATION UNIT NO. 1
~
REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 10 Data Table Variable Item No.
Accumulacor Tank Level D3 Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification The primary function of these indications is to assure adequate volume in the accumulators prior to any transient requiring injection. This indication, in conjunction with accumulator tank pressure and outlet isolation valve position indication, will ensure that these accumulators are capable of performing their safety function which is to inject water into the cold legs upon major depressurization of the RCS.
Assuming that the isolation valves are open, there is no action that the 4
operating crew can take in an accident situation if these accumulators do not perform their intended safety function. _ Therefore, this instrumentation does not have to be designed for accident-monitoring service.
The only operator action relative to the accumulators in an accident situation is to isolate them. The instrumentation used to rake this determination is RCS hot leg temperature and RCS subcooling. If RCS subcooling is greater than 80 F, and RCS hot leg temperature is less than 400 F, then the operator is directed to isolate the accumuistor. This action occurs whether or not the accumulator has discharged. The successful 7A-10
^
. I SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Justification (cont'd) completion of this step requires monitoring the position of the f. solation valves. If an isolation valve fails to fully close, then the oparator is directed to vent the unisolated accumulator by opening the vent valves. An open vent valve is sufficient to determine successful completion of this step.
The Seabrook-specific ERPs do not require that the operating crew monitor accumulator level in an emergency; therefore, it is not considered AM1.
SEABROOK STATION UNIT NO. 1
~
REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 11 Data Table Variable Item No.
Accumulator Tank Pressure D4 Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification The primary function of this instrumentation is to assure that the accumulators are pressurized to their normal operating pressure during plant operation. This indication, in conjunction with accumulator level and outlet isolation valve position, will ensure that these accumulators are capable of performing their passive safety function which is to inject water into the cold legs upon major depressurization of the RCS.
Assuming that the isolation valves are open, there is no action that the operating crew can take in an accident situation if these accumulators do not perform their intended safety function. Therefore, this instrumentation does not have to be designed for accident-monitoring service.
The only operator action relative to the accumulators in an accident situation is to isolate them. The instrumentation used to make this determination is RCS hot leg temperature and RCS subcooling. If RCS subcooling ir scrater than 80 F, and RCS hot les temperature is less than 400 F, then the operator is directed to isolate the accumulator. This action occurs whether or nct the accumulator has discharged. The successful completion of this step requires monitoring the position of the isolation valves. If an isolation valve fails to fully close, then the operator is directed to vent the unisolated accumulator by opening the vent valves. Open l
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SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Justification (cont'd) vent valve position indication is sufficient to determine successful completion of this step.
The Seabrook-specific ERPs do not require that the operating crew to monitor accumulator pressure in an emergency; therefore, it is not considered AMI.
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i 7A-13 L
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 12 Data Table Variable Item No.
Pressurizer Relief Tank Temperature D15 (Quench Tank Temperature)
Deviation From Regulatory Guide 1.97 Guidance The actual range (50-250 F) deviates from the recommended range (50-750 F).
Position The Pressurizer Relief Tank (PRT) temperature measurement is used in conjunction with PRT level and pressure indication to determine if PRT conditions are " normal." This determination is used to aid the operating crew in event diagnosis.
The temperature range provided is sufficient to indicate a change from normal operating conditions. Fully enveloping the expected temperatures to be encountered is not necessary in this case.- The operating crews will be made aware of the limitations of this measurement in their training program.
Therefore, this instrumentation is adequate for the required monitoring function.
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 13 Data Table Variable Item No.
Containment Spray Flow D23 (a) Containment Spray Pump Suction Pressure (b) Containment Spray Pump Discharge Pressure Deviation From Regulatory Guide 1.97 Cuidance A direct indication of containment spray flow is not provided.
Justification Containment spray pump head can be determined from the containment spray pump suction and discharge pressure indications provided side by side on the MCB. The operating crews will be trained in the use of this instrumentation to verify proper operation of the Containment Spray System. Quantitative determination of flow is not required to support the Seatrook-specific ERPs.
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1 SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 14 Data Table Variable Item No.
Containment Atmosphere Temperature D25 Deviation From Regulatory Guide 1.97 Guidance The range of the Containment Air Temperature Monitoring System is 50 F to 420 F versus the recommended range of 40 F to 400 F.
1 Justification The minimum containment air temperature will be greater than 50 F when this instrumentation is required to function (during and/or after an accident). Therefore, the range of this instrumentation is adequate for its intended monitoring function.
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7A-16 l
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SEABROOK STATION UNIT NO. 1
- REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 15 Data Table ,
Variable Item No.
Containment Sump Water Temperature D26 Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification I Seabrook-specific ERPs do not require that the operating crew monitor containment sump water temperature; therefore, it is not considered AMI.
t 7A-17
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 16 Data Table Variable Item No.
Makeup Flow-In D27 Deviation From Regulatory Guide 1.97 Guidance Makeup flow-in is classified as a Dasign Category 3 variable as opposed to Design Category 2 in Regulatory Guide 1.97.
Justification Normal charging and letdown is not required in the mitigstion of design basis accidents. It is classified as a nonsafety system and is used to assist in recovery if it can be placed in service. Therefore, the monitoring of charging flow is classified ar. Dusign Category 3.
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O SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 17 Data Table Variable Item No.
Letdown Flow-Out D28 Deviation From Regulatory Guide 1.97 Guidance
" Letdown flow-out" is classified as a Design Category 3 variable as -
opposed'to Design Category 2 in Resclatory Guide 1.97.
Justification Normal charging and letdown is not required in the mitigation of design basis accidents. It is classified as a nonsafety system and is used to assist in recovery if it can be placed in service. Therefore, the monitoring of letdown flow is classified as Design Category 3.
(..
SEABROOK STATION UNIT NO. 1 REGULATORY CUIDE 1.97, REVISION 3 REVIEW Leviatien No. 18 Data Table Variable Item No.
Volume Control Tank Level D29 Deviation From Regulatory Guide 1.97 Guidance
- 1. Volume control tank level is classified as a Design Category 3 variable as opposed to Design Category 2 in Regulatory Guide 1.97.
- 2. The range of this measurement.is 0 inches - 80 inches versus a recommended range of top to bottom (141 inches total).
Justification
- 1. Normal charging and letdown are not required in the mitigation of design basis accidents. If charging and letdown can be re-established, then they will be used to assist in the recovery. Therefore, the volume control tank level is not required for accident-monitoring service. It will be used only if charging and letdown are re-established. Therefore, the monitoring of Volume Control Tank Level is classified as Design Category 3.
- 2. The level channel monitors the straight shell portion'of the tank only.
The hemispherical heads are not monitored, since the volume to level ratio is not linear. The range of this channel is acceptable for the intended monitoring functions.
1 7A-20 S
e - . , y , - - ,,y p r- , - . .-
SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 19 Data Table Variable Item No.
Component Cooling Water Temperature D30 Deviation From Regulatory Guide 1.97 Guidance The actual range (O F-175 F) deviates from the recommended range (40 F-200 F).
Justification The maximum design temperature for componer.t cooling water under accident conditions is 120 F. The actual range envelopes this temperature with substantial margin. Therefore, this instrumentation is adequate for the required monitoring function.
f 7A-21
SEABROOK STATION- UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 20 Data Table Variable Item No.
High-Level Radioactive Liquid Tank Level D33 Deviation From Regulatory Guide 1.97 Guidance The range of this measurement is (0-14 feet) versus a recommended range of top to bottom of the tank (18 feet total).
Justification The range covers the top 14 feet of these tanks. The bottom section of the tank is hemispherical. The volume-to-level ratio is not linear in this region, therefore, is not in the span of the instrument. The range is acceptable for the intended monitoring function.
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SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 21 Data Table Variable Item No.
Dissolved Oxygen in Primary Coolant E18 (Grab Sample)
Deviation From Regulatory Guide 1.97 Guidance The 0 e neentration in the Primary Coolant System is not analyzed.
2 Justification NUREG-0737, Item II.B.3, criterion (4) states that measuring 0 concentration is recommended but not mandatory. In NHY letter from J. DeVincentis to G. W. Knighton, SBN-648, dated April 16, 1984, the clarification on Criterion (4) provided by the NRC staff to NHY was restated as follows:
{
NRC Criterion (4) Clarification The determination of dissolved oxygen can be satisfied by analyzing a post-accident gas sample from the Reactor Coolant System for dissolved hydrogen. If the reactor coolant dissolved hydrogen concentration is greater than 10 cc/kg, the NRC considers the dissolved oxygen level to be less than 100 ppb. If the post-accident dissolved hydrogen level is less than 10 cc/kg, the NRC will require NHY to provide justification that no damage to plant systems has occurred prior to plant startup, but considers the analysis requirement for oxygen satisfied.
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SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Justification (cont'd)
The NHY response was as follows:
NNY Response The amount of dissolved gases in the reactor coolant will be determined by extracting a gaseous sample from the post-accident sampling panel using a shielded syringe if necessary. This sample will be analyzed for hydrogen and gamma spectrum only.
This has been accepted in the Safety Evaluation Report, Supplement 3 Section 9.3.4.3.
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SEABROOK STATION UNIT NO. 1
. REGU'.ATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 22 Data Table Variable Item No.
RHR Heat Exchanger Outlet Temperature D2 Deviation From Regulatory Guide 1.97 Cuidance The lower end of the temperature range extends down to 50 F as opposed to a recommended lower end of 40 F.
Justification The RHR heat exchangers are cooled by the component cooling water system. The normal operating temperature is 85 F, automatic temperature control is provided by a safety-related temperature control loop. VAS alarms are provided should the temperature of the component cooling water drop below 75 F. This allows sufficient time for corrective action before the component cooling water temperature drops to 60 F, which is the minimum temperature for this system. Thus, the installed range is adequate since it will remain on-scale at all times.
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SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 23 Data Table Variable Item No.
Containment Drainage Sump Water Level B12A Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification Containment drainage sump water level instrumentation is provided that meets the guidance in Regulatory Guide 1.45, Reactor Coolant Pressure Boundary Leakage Detection System and NUREG-0737, Item II.F.1. The purpose of these instruments is to detect abnormal leakage into the containment when the leakage rate is insufficient to actuate the engineered safety features (Condition II events).
The Seabrook-specific ERPs do not require that the operating crew monitor this variable during a design basis accident event; therefore, it is not considered AMI.
SEABROOK STATION UNIT NO. 1
- REGULATORY CUIDE 1.97, REVISION 3 REVIEW Deviation No. 24 Data Table Variable Item No.
Pressurizer Heater Status, Power Monitor D13 Deviation From Regulatory Guide 1.97 Guidance This variable'is designated as Design Category 3, as opposed to Design Category 2 in Regulatory Guide 1.97.
Justification Pressurizer heaters are not required for the mitigation of design basis accidents. They are classified as nonsafety related and are used to assist in recovery if they can be placed in service. Therefore, the monitoring of pressurizer heater status is classified as Design Category 3.
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l SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 25 Data' Table Variable Item No.
Heat Removal by the Containment Fan Heat Removal System D24 1
Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification 8
1 Operation of the containment fan / coolers is not required for the mitigation of design basis accident events. The Seabrook-specific ERPs do not require that the operating crew monitor this variable in an emergency; ,
therefore, it is not considered AMI.
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l SEABROOK STATION UNIT NO. 1 REGULATORY GUIDE 1.97, REVISION 3 REVIEW Deviation No. 26 Data Table Variable Item No.
a Radioactive Gas Holdup Tank Pressure D34 I Deviation From Regulatory Guide 1.97 Guidance This variable is not considered AMI.
Justification l
Holdup of radioactive gas for decay is provided by carbon delay beds instead of pressurized storage tanks. Therefore, this variable is not applicable.
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i SBN-864 ATTACHMENT III (FSAR SECTION 1,8)
MARK UP
SB 1 & 2 Anondment 53 I FSAR August 1984 Regulatory Guide 1.96 Design of Main Steam Isolation Valve (Rev. 1, 6/76) Leskage Control Systems for Boiling
- Water Reactor Nuclear Power Plants This regulatory guide is not applicable to Seabrook Station.
Regulatory Guide 1.97 Instrumentation for Light-Water-Cooled fo r /774 Nuclear Power Plants to Assess Plant Con-ditions During and Following an Accident l
+4 The presen y identified pos ccident monitori (PAM) instrumentat' n c omplie ith the guidance rovided in Regula ry Guide 1.97, Rev. , with excep ons as discussed elow:
/
- 1. The maxi a range of the rad
- tion level measure nt inside contain-107 R/hr vs. 108 ment r reconunended by e Reg. Guide.
- 2. T maximum range of e reactor coolant ressure measurement 3000 peig vs. 3 ti s design pressure commended by the Re Guide.
- 3. The prima ent stack radiati monitor is single e nnel vs.
redundan channels recommend by the Reg. Guide.
For Items I a 3, the installed
- strumentation compl* s with the require ts of NUREC 07 , Item II.F.1. -
For I 2, the reconenend range of 3 times d ign pressure is unr listic due o the design of t reactor coolant sys m. Overpressure p tection is
{
p vided by power op sted relief valves RV's) and code saf y valves.
ie PORV's receive signal to open at 35 psig and the sa ty valves begin to open at 2485 sig, the system des
- n pressure. The p esure measurement ranges up to 0% of design press e (3000 psig) whic s adequate based system des
- n.
The d ign of the PAM ins mentation includes edundant channels r monitored /
va
- bles; both channel are indicated whil one channel is rec ded. The a
M instrument chann a are environmental and seismically alified and are fed from the rgency power supp1* s.
A complete d cription of the PAM notrumentation is rovided in FSAR ction 7.5.
PSNil in the 1,rocess of lecting the post- cident monitorin PAM) ins unentation vis-a-v' the guidance of I/ANS-4.5-1980, " riteria for l p
cident Monitoring F ctions in Light W er Cooled Reacto ," as endorsed by Regulatory Gutd .97, Revision 3. l n
4449 I
REPLACE WITH- ATTACiteD M/SERY A
)
1.8-36 i
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INSERT A Regulatory Guide 1.97 Instrumentation for Light-Water-Cooled (Revision 3 May 1983) Nuclear Power Plants to Assess Plant Conditions During and Following an Accident-Figulatory Guide 1.97, Revision 3 endorses ANSI /ANS-4.5-1980, " Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors." With minor exceptions, the above guidance has been followed in selecting accident monitoring instrumentation. These exceptions are provided in Subsection 7.5.4.
A complete description of the Seabrook AMI is provided in Section 7.5.
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