View source for ST-HL-AE-1480, Forwards marked-up FSAR Chapter 7 Pages Re safety-related Display Instrumentation in Response to Draft Ser/Fsar Items F 7.5-1,7.5-21 & 7.5-22.Pages Will Be Incorporated Into Future FSAR Amend

{{Adams
| number = ML20134A030
| issue date = 10/29/1985
| title = Forwards marked-up FSAR Chapter 7 Pages Re safety-related Display Instrumentation in Response to Draft Ser/Fsar Items F 7.5-1,7.5-21 & 7.5-22.Pages Will Be Incorporated Into Future FSAR Amend
| author name = Wisenburg M
| author affiliation = HOUSTON LIGHTING &amp; POWER CO.
| addressee name = Knighton G
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000498, 05000499
| license number = 
| contact person = 
| case reference number = CON-#485-019, CON-#485-19
| document report number = OL, ST-HL-AE-1480, NUDOCS 8511040069
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 84
}}

=Text=
{{#Wiki_filter:.
The Light COmpBM7 m><ium,ugamigmm miwx nm m>uumimxaa7mi mamsmii October 29, 1985 ST-HL-AE-1480 File No.: G9.17 Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC      20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Responses to DSER/FSAR Items Concerninn Chapter 7 on Safetv-Related Disolav Instrumentation

==Dear Mr. Knighton:==

The attachments enclosed provide STP's response to Draft Safety Evaluation Report (DSCR) or Final Safety Analysis Report (FSAR) items.
The item numbers listed below correspond to those assigned on STP's internal list of items for completion which includes open and confirmatory DSER items, STP FSAR open items and open NRC questions. This list was given to your Mr. N. Prasad Kadambi on October 8, 1985 by our Mr. M. E.
Powell.
The attachment includes mark-ups of FSAR pages which will be incorporated in a future FSAR amendment unless otherwise noted below.
The items which are attached to this letter are:
Attachment        Item No.*                       Subject 1          F 7.5-1               Safety-Related Display F 7.5-21              Instrumentation F 7.5-22 1
10     h        p
* Legend             6 D    DSER Open Item           C - DSER Confirmatory Item F - FSAR Open Item            Q - FSAR Question Response Item                       l i
Ll/DSER/aav l
                                                                                     'Il

7 Houston Lighting & Power Company ST-HL-AE-1480 Fil,e No.: G9.17 Page 2 If you should have any questions concerning this matter, please contact Mr. Powell at-(713) 993-1328.
Very truly yours, l
M. R. Wiseqburg Manager,NuilearLicens[ing MEP/bl-Attachments:         See above w
L1/DSER/aav             ,

ST-HL-AE-1480                C File No.: G9.17 Page 3 cc:
Hugh L. Thompson, Jr., Director                Brian E. Berwick, Esquire Division of Licensing                        Assistant Attorney General for Office of Nuclear Reactor Regulation                  the State of Texas U.S. Nuclear Regulatory Commission             P.O. Box 12548, capitol Station Washington, DC 20555                          Austin, TX 78711 Robert D. Martin                               Lanny A. Sinkin Regional Administrator, Region IV              3022 Porter Street, N.W. #304
             ' Nuclear Regulatory Commission                Washington, DC 20008 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011                           Oreste R. Pirfo,_ Esquire
                           .                                Hearing Attorney N. Prasad Kadambi, Project Manager            Office of the Executive Legal Director
             .U.S. Nuclear Regulatory Commission        U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue                          Washington, DC 20555 Bethesda, MD 20814 Charles Bechhoefer, Esquire Claude E. Johnson                             Chairman, Atomic Safety &
Senior Resident Inspector /STP                       Licensing Board c/o U.S. Nuclear Regulatory                   U.S. Nuclear Regulatory Commission Commission                               ' Washington, DC 20555 P.O. Box 910 Bay City, TX 77414                            Dr. James C. Lamb, III 313 Woodhaven Road M.D. Schwarz, Jr., Esquire                    Chapel Hill, NC 27514 Baker & Botts One Shell Plaza
                                                           ' Judge Frederick J.~Shon Houston, TX 77002                             Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission J.R. Newman, Esquire                          Washington, DC 20555 Newman & Holtzinger, P.C.
1615 L Street, N.W.                          Mr. Ray Goldstein, Esquire l             Washington, DC 20036                          1001 Vaughn Building 807 Brazos Director, Office of Inspection               Austin, TX 78701
;                and Enforcement.
'-            U.S. Nuclear Regulatory Commission            Citizens for Equitable Utilities, Inc.
Washington, DC 20555                       .c/o Ms. Peggy Buchern Route 1, Box 1684 E.R. Brooks /R.L. Range                      Brazoria, TX 77422 Central Power & Light Company l
P.O. Box 2121                                Docketing & Service Section l             Corpus Christi, TX 78403                     office of the Secretary U.S. Nuclear Regulatory Commission H.L. Peterson/G. Pokorny                    Washington, DC 20555 City of Austin                                (3 Copies)
P.O. Box 1088 Austin, TX 78767                            Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission i             J.B. Poston/A. vonRosenberg                  1717 H Street l             City Public Service Board                   Washington, DC 20555 j             P.O. Box 1771
!             San Antonio, TX 78296 l                                                                                         Revised 9/25/85 L1/DSER/aav I:

ATTACHMENT I STP FSAR            ST-HL AE 14fD PAGE r OF gl TABLE 1.1-1-(Continued)
ACRONYMS USED~IN THE FSAR LPG          liquid petroleum gas LPMS   .
Loose Parts Monitoring System                                l39 LPZ          low population zone                               ~
LRPT         lead radiation protection technician                         38 LRTS Liquid Radwaste Treatment System LSA         low specific activity LTMD less than minimum detectable (concentration)
LVDT linear variable differential transformer LWPS         Liquid Waste Processing System MAB         Mechanical Auxiliary Building MCARS       Main Condenser Air Removal System i                                                                          l39 MCB         main control board MCC         motor control center MCR          Main Cooling Reservoir l35 MDC          moderator density coefficient MDWS Makeup Demineralized Water System MEAB Mechanical-Electrical Auxiliaries Building MEB          Mechanical Engineering Branch Mg7         N eT.eerolo3mm) 53 stem                                            g MFIV main feedwater isolation valves                             41 MG           motor generator MIL         military standards MLW         mean low water MOL        . middle-of-life MOV        . motor-operated valve ME:         maximur permissible concentration 1.1 -11.               Are nc --

STP FSAR
           ~
ATTACHMENT I ST.HL AE- N P PAGE 7- OF 3)
Qusation 032.17 j State your conformance with Regulatory Guide 1.97 " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident." Justify any exception taken.
     , Response As stated in Table 3.12-1, STP conforms to the intent of Regulatory Guide 1.97, Revision 2 (12/80)4eith..gt the guid; is ee: pplicati :; ST" I;; :c     40 it   4 71 --- t st i-- data A detailed discussion of post-accident monitoring instrumentation is presented in Section 7.5 and Appendix 7B.
0 1
Q&R 7.5-1                   ^*d*!      '

                                                                                        ,=,
4 TABLE 3.12-1 (Continued)
REGUIATORT GUIDE NATRIK RECUI.ATORY CUTDE
     ,1uf.                             TITLE                                        FSAR REFERENCE   REVISION STATUS    STATUS ON STF 1.97      Inst rumentation for Light-Water-Cooled Nuclear Power               Table 7.1-1       Rev 2 (8/77)    '5 See Note a      64 40      N Flsnts to Assess Plant conditions During and                        Figure 7.1-1 Pollowing an Accident Table 7.5-1                                                        .
App. 7A App. 75 I.98      Assumptions Used for Evaluating the Fotentist                                                           WA See Note 1 Radiological Consequences of a Radioactive Offges System Failure in a Bolling Water Reactor 1.99      Ef f ects of Residual Elements on Fredicted Radiation               5.3.2.1           Rev 1 (4/77)      D See Note 57       l33 Damage to Reactor Yessel Materists en 1.100     Seismic Qualification of Electric Equipment for                     Table 7.1-1       Rev 1 (8/77)     .5 See Note' 3       l36          Q
,,              Nuclear Power Plants                                                Figure 7.1-1                                                         m
:.                                                                                  3.10.1 3.10.2.2                                                         ,o      )g k
3.10.2.2.1                                               43      3*      q 3.10.2.2.2.2                                                             3, 3.10.4.1                                                              .O d)> I 1.101     Fmergency F1saning for Nuclear Power Flants                         9 5.1.A pg 18     withdrawn            See Note 37      l32              %
1.102     Flood Protection for Nuclear Power Fleets                           3.4               Rev 1 (9/76)      A                                k-4 3.8.4.2.3                                                33      % O_
l.103     root-Tensioned Frestressing Systems for Concrete                    3.8.1.2.2         Rev 1 (10/76)     A                   l45 Pentter Vessels and Containments                                   3.8.1.6.5.1 1.104     ovenbead Crane Band 11ag Systems for Nuclear Power                   9.1.4.3.1.6      Rev 0 (2/76) FC   3 See Note 34       ly3 riants                                                             Table 9.1-3 1.10's     Instrument Setpoints                                               Table 7.1-1       Rev 1 (11/76)     B See Note 3 Figure 7.1-1                         ,
Note 28          l33 q     1.106    Therral Overload Protection for Electric Motors on                   8.3.1.2.12       Rev 1 (3/77)      A See Note 14           'I
  ~,             Hot or-operated Valves                                              8.3.2.2.7                                              l18 l Q430.
u                                                                                                                                              130N 1.107     S'nlifications for Cer?nt Crouting for Frestressing                                                    NA See Note 11      l23 1rndone in Containment Structures t.in4     r.viedic Testing of Diesel Ceneratore Used as Onsite                8.3.1.1.4.7      Rev 1 (8-77)      C See Note 40       l38 t lert ric Fever Systems at Nuclear Power Plante                    8.3.1.2.10
: 1. t fiq  r itrulat ions of Annust Doses to Man From Routine                  ll.A.1           Rev 0 (3/76) FC   A Pelenses of Resctor Ef fluents for the Furpose of                   12.4.2           Rev 1 (10/77)                         l32 t vnluating Compliance with 10CFR$0, Appendix I

ATTACHMENT 1 STP FSAR           ST-HL-AE N80 PAGESt OF fl TABLE 3.12-1 (Cont'd.)
         !                                                                  REGULATORY GUIDE MATRIX NOTES                            -
If a work activity and contract is for a two-month period or less,        43 an audit is not necessary when a facility preaward audit has been conducted.
                                                 ,: The QA program for operations will conform to the requirements of RG 1.94      45 Revision 1, with the same clarification:
: 55. Refer to Sections 3.7.4.1 and 3.7.4.2 for the discussion on seismic instrumentation.
: 56. Refer to Section 5.2.3.3.2 for Westinghouse alternate approach to RG 1.71. Also, refer to Section 10.3.6.2, for the BOP conformance to RG 1.71.
: 57. STP alternate approach to RG 1.99 is discussed in Section 5.3.2.1.
: 58.         STP alternate a'pproach to RG 1.121 is discussed in Section 3.12.1.
: 59. Revision 0 is utilized during the construction phase for RG 1.58, Posi-tions C.5, C.6, C.7, C.8, and C.10 of Rev. 1 are also utilized.                33 1
: 60. With respect to Section 3.1.2 of ANSI N45.2.3-1973 HL&P interprets the
         )                                          lighting level of 100 footcandles to be guidance. It is HL&P's normal practice that the lighting level for determining " metal clean" of acces-sible surfaces of piping and components is determined by the inspector.
Typically he uses a standard two-cell flashlight supplemented by other lighting as he deems necessary.
: 61.         STP conforms to RG 1.140, with the exception that instrumentation is provided only to monitor and alarm pertinent pressure drops at critical points in the duct. Therefore, STP is in partial compliance with Position C.2.cc.
38
.                                       62.         RG 1.1 as clarified by NUREG 75/087.
.                                       63. The basis for meeting the intent of RG 1.46 is the implementation of NRC Branch Technical Position (BTP) MEB 3-1, NRC BTP ASB 3-1, WCAP-8082-P-A, and WCAP-8172-A. Tables 3.6.1-2 and 3.6.1-3 provide a summary of the compliance with MEB 3-1 and ASB 3-1.                              -
40
: 64. Eweepti;;; w re -isic,n 2 cre identified in -TS".%. eefer;;;; :: ti;;;.--C"~
: 65. The QA program during operations will conform to the requirements of Revision 2.
: 66. The QA program for operations will conform to the requirements of                     43 Position C.2 of Regulatory Guide 1.137 with the following clarification:
                                                                                                                     %e 7 514,i,I Tks. clise:=En ef GTP ca Nrmsace,. -le & G l.97 AM.2. is presukul i3 &ncks M.
4s e+fW in Appucks 78, ;ylmbb, s/ RC 1.97 reg uirM sa , ;4yaled w.'& Os.culvel coe,= cMy twisa a-cl a pufr< red g & k/ TAW Amendment 45 i                                        Owas s Cray Fe% Acapua.Cujf,.12-24Dna% a.d emb w,*& & kW / & Ag,
___.____.-.___u___.__

STP FSAR    ATTACHMENT i                 ]
ST-HL-AE- N30 PAGE G OF S t 7.5 Safety-Related Display Instrumentation 7.5.1       Post Accident Monitoring Instrumentation 7.5.1.1 Description. A task analysis was conducted to identify the appropriate variables and establish appropriate design bases and qualification criteria for, instrumentation employed by the operator for monitoring condi-tions in the Reactor Coolant System (RCS), the secondary heat removal system,
-and,the Containment, including Engineered Safety Features (ESF) and other                  40 systems normally employed for attaining and maintaining a safe shntdown condition. The instrumentation is used by the operators to monitor the South Texas Plant throughout various opp ating conditions including anticipated operational occurrences and possaccident conditions. The analysis process                    )(
ensures that the information available to the operator following an accident is derived from specially designed and qualified instrumentation installed at the plant.
7.5.1.2    Analys *.s . The task analysis performed in response to Regulatory Guide (RG) 1.97 is described in Appendix 7B. Table 7.5-1             provides   40 a listing of the variables identified in the task analysis.          In addition, the      Q32.
table includes the following information on the STP instrumentation utilized               18 for each variable: (a) instrument range; (b) type and category (per the defi-nitions found in Appendix 7B); (c) environmental qualification; (d) seismic qualification; (e) number of channels available; (f) display device and loca-tion; (g) the schedule for implementation; (h) power supply; and (i) a state-ment of conformance to RC 1.97, Revision 2, or justification for deviations.
Seismic and environmental qualification3sare further discussed in Section$ 3.10               )(
and 3.11.
To assist in understanding the information provided in Table 7.5-1, the fol-lowing explanation of column headings is provided:
Variable: This column contains the RG 1.97 variable as defined in Appendix 7B.
Range / Status: This column contains the range of instruments used on STP for RG 1.97 purposes and a description of STP indications of valv,e position or                40 pump status. The ranges indicated meet or exceed the requirements described in Appendix 7B.
Type / Category: This column contains the types and categories applicable to each variable as defined in Appendix 7B.
Indicate,5 Environmental and Seismic Qualification: This column 3::::i5:: whether or not               )(
the STP instrumentation is seismically or environaentally qualified. A "yes" in the Environmental Qualification column indicates that the channel is envi-ronmentally qualified to a level which meets or exceeds the requirements spec-ified in Appendix 7B for that variable.
Number of Channels:    This je lumn contains the number of instrument channels available on STP for post 5 accident monitoring purposes. This column does not              )(
take into account control room indication or recording capability.           The number 7.5-1                    Amendment 40

M e & MLMMLIN i j STP FSAR            l ST HL-AE- Nfo l
                                                          'PAGEfo OF $                      '
1
                                                                                            \
cf channale cveilcbla ments or cxceeds the rcquir m:nts in App ndix 7B, except for the cases in which justification for deviation from Appendix 7B is                      l provided in Table 7.5-1.
                                                            ;g,jggg7}g' t
Control Room Indication: This column describes th control room indication                    '
cnd recording capability on STP for each variable. The control room indica-        N tion and recording capability meets or exceed $the requirements described in        )(
Appendix 7B.        ,
4 Implementation Date: This column contains the STP schedule for implementing the RG.
Power Supply: This column describes the power supply which powers the STP instrumentation for each variable. The power supply provided meets or exceeds the requirements described in Appendix 7B.
cewter    Eoc.                              Fen A* 5 Emergency Operations Facilit:. (.EGE) Indication: This column describe: the STP      I Emergency Operations Facility indication capability for each variable.               /
Ceniee                               p.ch Technical Support Center (TSC) Indication: This column d::crih:2 the STP               X Technical Support Center indication capability for each variable.
Conformance: This co'umn provides a statement of the conformance to RG 1.97, Revision 2 or justification for deviation.
Further information concerning conformence to RG 1.97, Revision 2 is provided in Appendix 7B, which describes (a) the plant accident conditions under which   40 the instrumentation must be operable; (b) the selection criteria (Type A, B, C, D, or E); (c) the qualification criteria (Category 1, 2, or 3): (d) the design criteria (number of channels, power _ requirements, servicing requirements, etc); and (e) the processing and display criteria (accessibility, historical record, etc.).
The postd5ccident monitoring instrumentation consists of the instrumentation            N identified in Table 7.5-1. The display systems for the post-accident monitoring instrumentation are identified in Table 7.5-1 and are further described in the sections identified below:
: 1. Qualified Display Processing System (QDPS) - Section 7.5.6.
: 2. Emergency Response Facilities Data Acquisition and Display System (ERFDADS) - Section 7.5.7.
: 3. Radiation Monitoring System (RMS) - Section 11.5. later                           N A
7.5.2      Reactor Trip System Display instrumentation for monitoring during normal operation in the Reactor Trip System is discussed in Sections 7.2 and 7.7.
7.5.3      Safe Shutdown Display instrumentation provided for monitoring safe shutdown during normal operations is discussed in Section 7.4.                                                   b 7.5-2                Amendment 40

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ATTACHMENII ST HL AE IW' STP FSAR        PAGE t OF 3l r
         . Visual indication (t(ough lampbox lights) that specific ESF equipment has g
-- 1.
been bypassed or deliberately rendered inoperable during normal plant operating modes.                                                                    '
: 2. Annunciation to alert the operator that an ESF system or any of its support systems has been bypassed or deliberately rendered inoperable during normal plant operating modes.
The bypa,ss/ inoperable status indication subsystem continuously monitors the status of field' contacts and automatically indicates that a specific piece of ESF equipment has been bypassed or deliberately rendered inoperable. The fol-lowing conditions (as applicable) are automatically detected for each moni .
tored component of the ESF systems:
: 1. Loss of control power l
: 2.      Control handswitch in pull-to-lock position                                l
: 3.      Circuit breaker no't in operating position
: 4.      Control transferred from the control room to a remote panel 5 .'   Component not-in its proper aligned position The bypass / inoperable status indication is accomplished by lighting up the       l 41 component level window. This indication also provides individual system level !
annunciation to alert the centrol room operator that an ESF system has been
   . bypassed or rendered inoperable.
In accordance with RG 1.47, bypass or inoperable status indication is provided automatically for conditions which meet all three of the following guidelines:
: 1. The bypass or inoperable condition affects a system that is designed to automatically perform a safety-related function.
: 2. The bypass is utilized by plant personnel or the inoperable condition can reasonably be expected to occur more frequently than once per year and,-
: 3. The bypass or inoperable condition is expected to occur when the affected system is.normally required to be operable.
Deliberate manual actions which render ESF actuated components and devices inoperable (once a year or more frequently) are automatically displayed on a component level. -Active components not directly' actuated by ESF signal but rendered inoperative once a year or more frequently such that it compromises the safety functions of the ESF system are also automatically displayed on a component level to the control room operator.
Rendering a piece of ESF equipment inoperative through the use of features provided strictly for infrequent maintenance (less than once a year) is not automatically indicated. Such maintenance features may include manual valves provided for isolation of the equipment for repair and electrical cable con-nections, screw terminals or manual disconnects. The bypass / inoperable indi-cation of these conditions is manually initiated on an ESF system level.
l 7.5-4                                Amendment 45 1
l H

ATTACHMENT i ST HL AE-N80 STP FSAR       PAGE 9 OF PI The capability for initiating a manual bypass indication and          larm is         _I provided via a system level manual bypass switch to indicate the bypass /in-oper?ble condition to the operator for those components or conditions which        ;g are not automatically monitored.
Manual bypass / inoperable indication may be ' set up or removed under administra-
                -tive control.- The automatic indication feature of the ESF Status Monitoring System can not be removed by operator action.                       -
Bypssand[orstatusindicationonasystemlevelisprovidedforthefol-lowing safety-related systems:
                           ~
: 1. Solid-State Protection System (bypass / inoperable only) 41 2 .~  Safety Injection System (SIS) (including RHR system components required
     ~P                for accident mitigation or safe shutdown)
: 3. Containment Spray System (CSS)
: 4. Containment-Isolation Phase A
: 5. Containment Ventilation Isolation                                            41 Q3
: 6. Class IE 125 vde and 120 v Vital AC Systems
: 7. Combustible Gas Control System (bypass / inoperable only)
: 8. Containment Heat Removal System
: 9. Fuel Handling Building (FHB) Iheating,3 ventilating, and Iaic     nditioning        X (HVAC) Exhaust Subsystem
: 10. Electrical Penetration Space HVAC System
: 11. Control Room Envelope and Electrical Auxiliary Building (EAB) Main Area HVAC System
: 12. Feedwater Isolation 41
               .13.. Steam Line Isolation d       14. Auxiliary Feedwater System (AFWS) b( cggc.y rg          is ,_ [g n i @ e.,       ,. Ed Af fmL            t                                     k v         The following support systems activate bypass indication of all supported safety systems. listed above when they are bypassed or rendered inoperable:
2
: 1. _  Component Cooling Water System (CCWS)
: 2. Essential Cooling Water System (ECWS)
: 3. ESF Bus System (including the standby diesel generators and the ESF load sequencers) l               4. Essential Chilled Water System 7.5-4a                         Amendment 41

STP FSAR           ATTACHMENLl ST-HL-AE NF PAGE(o 07 SI
: 5. Supportit.g HVAC equipment The ESF Status Monitoring System is not required to operate during or after a                    l4I        , ,
design basis seismic event; however, the indicator light panels are mounted on the seismically designed and qualified control benchboard. The indicator panels are designed and have been type tested to prove their structural integ-rity.               .
No credit is taken in the accident analyses of Chapter 15 for the ope.rability of the ESF Status Monitoring System. The system is not designed to safety-re-lated requirements. Interfaces with safety-grade equipment are through qual-                       41 ified isolation devices, in accordance with IEEE 384 and RG 1.75.                   These iso-lation devices are part of the Emergency Response Facilities Data Acquisition and Display System (ERFDADS) (see Section 7.5.7).
7.5.5       M: = 1 Op ucti;n: M;nitnin;Y(Deleted)                                                   I TM; infomatien haa teen p a ... Tobl                   7.5 [                                         )(
~7.5.6       Qualified Display Processing System 7.5.6.1     Descripti5n. The QDPS is an integrated system designed to perform the following functions:
: 1. Data acquisition and qualified displays for post-accident monitoring.
: 2. Safety grade control and position indication of several safety-related valves.
: 3. Data acquisition, display, and control to cddress the separation require-ments of the STP design approach to a control room (CR) or relay room (RR) fire.
4     Steam fenerator 1/arrov )(ange y'ater-} level compensation for the ef f ect of              40 y temperature changes in the reference leg fluid.                                                   I 5     ' "9 ' " 8 ' " "' ' "' " 8 "" ' 1 " " 4 " ' * * " * * " "" * " '" ' "' '* ")                     ,
7.5.6.1.1 System Description. The system functions are performed by         '
several subsystems. These subsystems, though related, have sufficient inde-pendence such that the individual functions can be performed with maximum reliability and minimum unnecessary interaction between functions. A block diagram indicating the interconnections of the various QDPS subsystems as well as interfaces with other systems is provided in Figure 7.5.6-1.
7.5.6.1.1.1 Data Acquisition and Qualified Display for Post Accident Monitoring - The data acquisition and qualified display function is performed by a subsystem referred to as Plant Safety Monitoring System (PSMS). It is a modular and flexible general purpose system which performs the following func-tions:
: 1. Implements qualified monitoring channels to comply with post-accident jX monitoring gategory / equipment design and qualification criteria defined in Appendix 7B.          ,i 7.5-4b                                 Amendment 41

ATTACHMENI (
2 STP FSAR ST HLt t AE PAGE     OF l@$
: 2. Provides safety grade signal processing for instrumentation to detect inadequate core cooling as defined in NUREG-0737 Item II.F.2. This includes signal processing for:
e      Reactor vessel water level e      Core exit temperature                                               ,
(;gyg e.  *fp*phk 78.lT,f.2 MAO & L.00 O m s' w .
: 3. IsolatefClass1Eandassociatedsignalstomakethemavailableto                                )(
non-Class 1E equipment including the Emergency Response Facilities Data Acquisition and Display System (ERFDADS) (see Section 7.5.7).
: 4. Providefconsolidated, unambiguous, human-factoreddisplaysofappropriate                  X arameters to address the requirements of paragraph 4.20 of IEEE 279-1971, e Figure 7.5.6-2    b6 Sche *% rgresenhh of synal processi q ^                    g
           @ Jispla3 cowsob ien .
The PSMS consists of four redundant, channelized,ClassdEdataacquisition                      T processors called remote processing units (RPUs). These RPUs send data to redundant data)ase processing innits (DPUs), which subsequently provide infor-                Y mation to the operator via plasma e splay modules. A fifth, non-Class IE RPU (RPU N) provides data acquisition for non-Class 1E signals which are needed to complete logical graphic displays. The RPUs perform the engineering units L conversion, limit checks, and isolation or buffering                     required. The DPUs performhensor algorithms and auctioneering functionl en output the data                     {0 4   base to the plasma display modules. The plasma' display modules provide graphic and alphanumeric display pages containing comprehensive, human engi-neered display information. Display page selection is performed using a fune-tion keyboard for each display module.
The variables required in the PSMS database are categorized into three types:
: 1. Safety grade parameters required to address post-accident and safe shutdown monitoring requirements.
: 2. Variables identified for monitoring the minimum functions required to achieve safe shutdown under postulated fire conditions.
: 3. Parameters included for display consolidation on the main control panels.
7.5.6.1.1.2    Safety Grade Control and Position Indication of Safety-Related Valves - The safety grade valve control function is perform (d by a microprocessor based control syste.        This consists of a set of Classs1E           )(
equipment used to provide the'followin process enntrol functions:
Eagle 23
: 1. Closed-loop control and position indication for the steam generator (SG) power-operated relief valves (PORV).
I
: 2. Contact output signals for automatic control and position indication of auxiliary feedwater (fv) er- m l valves within upper and lower flow                    K limits.               t           i A):y/        Oou,throMe,                  .
Amendment 40

ATTACHMEh@T ST  HL AE l'        u STP FSAR          ..fAGE & OFfl
: 3. Open-loop control and position indication for the reactor vessel head vent valves.              . .
4-
                                                                                  *
* N C5 F M    X Closect-leaIs.co eet & pe         me\ mM. foSfnon Indit4% n for EW flo w C8 " **l                       ,
The SG FORV control equipment provides hardware to meet the requirements for           x fullf valve control including transfer, without position change, of operation from the control room to the auxiliary shutdown panel. A separate transfer M cwitch selects the. active control station. Each control loop accepts the N cteam line pressure, valve position, and the setpoints as input variables and cutputs a 4-20 mA signal to control the valve.                                ,
Each auxiliary fee'dwater throttle vaJ1 e control loop accepts an input from a flow-transmitterandsuppliestwobigstableoutputsignals,lowandhigh                         X limit {,tothevalvecontroller. These signals maintain- - ___ , _ flow                    X within acceptable limits until manual control is assumed by the operator.
APr/
The reactor vessel head vent      nerol loop accepts signal inputs from a pair of manual stations, one located in the control room and the other on the auxiliary shutdown panel. A separate transfer switch for each loop selects the active re m el station.                                                          X g                   4- rnual 7.5.6.1.1.3 Data Acquisition, Display, and Control to Address Separation Requirements of the STP Design Approach to a CR or RR Fire - Signal buffering to meet fire protection isolation and separation requirements is achieved by using microprocessor based equipment, which provides interface with the NSSS process protection and control cabinets.
Field inputs for variables identified for monitoring the minimum functions           40 required to achieve safe shutdown following a CR or RR fire are routed to the QDPS auxiliary process cabinets (APCS). The signals are split into two inde-pendently buffered outputs. One of these outputs is routed to the process protection or control cabinets, and the other serves as an input to the RPU (see Figure 7.5.6-3). With this configuration, the QDPS displays of these parameters are available should any failure occur in the process protection or control cabinets or input and output cabling.
gt 7.5.6.1.1.4   Steam Generator Narrow Range 3 Level Compensatien and               X Display - The gteam penerator )(aryg ifange Vat'e'r yevel 7ompensation system automaticallycompensatestheSG$levelsignalsfortheeffect of temperature                    Y changes in the reference leg fluid. This system serves to increase operating margin and to improve the accuracy of post-accident   e    level indications. With referenceleg-temperatureeg*pensationoftheS6[evelsignals,therequired                      'd increaseinthelow-lows (*levelreactortripsetpoint to account for refer-                    X ence leg heat-up following a high energy line break inside containment is minimized. The compensation system is designed to limit the reference leg heatup error to 2 percent of the level instrument span. SG levels are dis-s   played on the                                                      indicators. For    X ry additional information, (j QPDG plasma     displays refer to   Section and 7.2. on main control      pane water                x
   -Y         m          QOf5
              /  7.5.6.1.2 Equipment

== Description:==
The QDPS consists of the following equipment: four Class 1E APCS, two Class 1E dajabase processing units, eight Class IE plasma display units, three non-Class 61E demultiplexer units, and one        X non-Class 1E RPU. Refer to Figure 7.5.6-1 for system configuration.
7.5-6                           Amendment 40

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ATTACHMENU STP GAR        ST HL AE IW PAGEg4 OF f!l 1.5.6.1.2.1 Auxiliary Process Cabinets - The four redundant APCS comply with IEEE 279-1971. Each channelized APC contains an RPU chassis, control system chassis, signal isolation / buffering equipment and associated DC power supplies for field inputs originating from this respective instrument channel.
Data is outputg via datalinks and individual analog signals as required. Each
  ) g ""t:rtalink is iiidependently buffered such that no fault on a datalink will de-P     grade system. function beyond loss of data on that link.         The APCS are located in four physically separated fire areas, such that no single fire will affect more than one APC. The APCS are powered from the four separate 120 vac vital instrument buses.
7.5.6.1.2.2     Database Processing Units (DPU) - The two redundant DPUs comply with IEEE    279-1971. Each DPU contains signal processing equipment, signal isolation / buffering equipment and the DC power supply.          The DPUs re-ceive data inputs from each of the RPUsg nd transmit data outputs to the Class 1Eplasmadisplayunits,non-Class 1FhMUE,andotherdestinationsasneces-                      T sary. Each datalink is buffered such that no fault on a datalink will degrade system function beyond loss of information carried on that link. The DPUs are located in physically separated rooms with she separation group A and C APCS, and are powered by the separation group A and C f 120 vac vital instrument              y buses, respectively.       Seper tier group: ^.(end C ccrresp nd t instruncnt chan nc1; I and I" scapcctively. j                   % ] neget M
  %ed As*
7.5.6.1.2.3 Plasma Displav Units - The eight plasma display units are grouped into two redundant sets of three display units each in the control room and the two redundant display units on the auxiliary shutdown panel. The           40 plasma display units conform to IEEE 279-1971.          Each plasma display unit con-tains the microprocessor equipment and DC power supplykto receive data from gg, each DPU and generate graphic and alphanumeric display pages. A function keyboard attached to each display unitfallows operator selection of specific             Y display pages. One redundant set of plasma display units is powered by the separation group A 120 vac vital instrument bus and the other set by separa-tion group C vital instrument bus.                                                      X CO 903 7.5.6.1.2.4 Demultiplexers - Two of the three DMUX units are located in the control room. The third DMUX unit is located in the auxiliary shutdown panel. The DMUX units are non-Class 1E devices which provide system outputs to drive analog panel meters and recorders. The units are seismically quali-fled in accordance with IEEE 344-1975 such that the recorder output will re-main functional following a seismic event.          The DMUX units are powered from the non-Class 1E instrument bus backed-up by station batteries.                           X k 1;LO ya.c Mod 7.5.6.1.2.5      Remote Processing Unit N (RPU N)     -
The single non-Class 1E RPU N provides data acquisition for certain non-Class 1E signals.           The RFU is not required to function post-accident and is not redundant.          RPU N is located in the relay roorthlectrical quxiliary guilding[EA glevation35kandis powered from the non-Class 1E instrument bus W
(, g m g A bat.ked up % sfcMon bodentS .
7.5.6.2     Analysis. Even though IEEE 279-1971 was not a design basis of the QDPS, an analysis was conducted to determine those criteria stated in the           g standard that were met by the system design.         The following sections discuss the applicability of the QDP,S to the respective sections of IEEE 279-1971. In performing this evaluation the functions performed by the QDPS are subdivided 7.5-7                  Amendment 49
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ATTACHMENT l STP FSAR            ST-HL.AE- MP PAGE Ft OF U hvoMO into the following subgroups:     (a) steam generator water level compensation I
cystem (SGVLCS), (b) ESF qualified controllers (e.g., auxiliary feadwater (AFW regul:::r calve control), (c) qualified controllers utilized for                     [
ac eving a safe shutdown, and (d) post-accident monitoring displays.
References to the QDPS from a system level in the succeeding discussion indicates that all QDPS subsystems meet the stated requirement. Furthermore,
                    ~
49 the applicability of the General Design Criteria (GDGs) are indicated below.
7.5.6.2.1 General Functional Requirement: This criteria only app'.ies to the SCVLCS -and the'ESF qualified controllers. Other functions do not automat-ically initiate appropriate protective action.
7.5.6.2.2    Single-Failure Criterion: The QDPS is designed to provide cdundant instrument channels for each safety-grade function as described in             40 Section 7.5.6.1. These redundant channels are electrically and physically independent. A single failure in the QDPS will not prevent proper response at the system level. The loss of power to any vital instrument bus will result ct most in loss of display from one channel. A failure modes and effects l49 enalysis has been performed and is presented in Table 7.5-4.      The design meets the requirements of GDC 21, 22, and 23.                                               40 7.5.6.2.3 Quality of Components and Modules: The QDPS meets the 99 percent availability requirement defined in NUREG-0696 Section 1.5 under all pressure and temperature conditions exceeding cold shutdown conditions.
l 49 7.5.6.2.4 Equipment Qualification: The QDPS is seismically and environ-          40 centally qualified to IEEE 344-1975 and IEEE 323-1974, and meets the require-ments of GDC 2 and 4 with the exception of RPU N which performs non Class 1E functions. The DMUX units are seismically qualifiad. Equipment qualification is also discussed in Sections 3.10 and 3.11.                                           49 7.5.6.2.5    Channel Integrity:  The QDPS is designed to operate during cccident conditions and maintain necessary functional capability and accuracy under extremes of conditions relating to environment, energy supply, malfunc-tions, and accidents.                                                                  40 7.5.6.2.6    Channel Independence:   Channels that provide signals for the    l 49
    =ame function are electrically independent and physically separated to accom-       i plish decoupling of the effects of unsafe environmental fectors, electric           l 40 transients, and physical accident consequences.      The system is designed to      l 49 minimize the potential for interactions between channels during maintenance         i 40 operations or in the event of channel malfunction.      The QDPS features two redundant physically separated independent trains of display.       The design cnsures that an initiating failure (short circuit, fault, etc.) in either a DPU or display unit will not result in the loss of both trains of DPUs and/or          49 display units. The design meets the requirements of GDC 22.
7.5.6.2.7 Control and Protection System Interaction: The only subsystem that is used for both protective and control functions is SGVLCS.       Further-more, control grade signals are output from the post-acident monitoring QDPS subsystem.
7.5-8                 Amendment 49

ATTACHMENT f STP FSAR         ST-HL AE Me PAGED OF 8l In all cases the transmission of signals from the QDPS for control or use by other non-Class 1E devices is through qualified isolation devices which are part of the QDPS system. Faults, such as short circuits, open circuits,                        l ground, or the application of credible AC or DC fault potential at the output                  j of an isolation device, will not prevent the associated protection system                      149 channel from m,eeting minimum performance requirements.
g ef**$ g Noise and isolation testing will be addressed in a WCAP,iv bs . b.itted ir tF-    ,
     ,.. _.. .. .       c ,noe This design meets the requirements of GDC 24                                                      40 13erivation
                           ": ! tier of System Inputs:       To the maximum extent practica-7.5.6.2.8                                                                               ]49 /k ble, the QDPS inputs are derived from signals that are direct measures of the monitored variables.                                                          co, pow,gt 4yug, 40 7.5.6.2.9 Capability for Sensor Checks: The QDPS bas built-in diagnos-tics for checking the operational availability of each system nput sensor                        K during reactor operation. This is achieved by continuous scanning by micro-processor b'ased sensor data quality checks. A data quality is assigned to all rede         channels of data input. The routine processes the redundant sensor                  X inputs and, when possible, returns a group value of the valid sensors for use in the upper level displays.
7.5.6.2.10       Capability I'or Test and Calibration:       The SGWLCS and ESF qualifieo controllers have the capability for testing and calibration during reactor operation. The post-accident monitoring subsystem has the capability for checking the operational availability for each channel during reactor operation by cross checking between channels that bear a known relationship to each other. The safe shutdown qualified controllers are only required to be tested during scheduled station shutdowns. Refer to Section 7.2.2.2.3.10 for
!     a description of the tesrf g of the protection loops.               The design meets the          49 requirements of GDC 21.
7.5.6.2.11       Channel Bypass or Removal from Operation: The SGWLCS sub-system is designed to permit all channels, one at a time, to be maintained,                           ,
tested, or calibrated during power operation with no loss of. safety function.
The ESF qualified controllers are designed to permit all channels, one at a time, to be maintained, tested, or calibrated during power operation. Access to the cabinets for removing channels from service is administrative 1y con-trolled.
7.5.6.2.12       Operating Bypasses:    There are no operating bypasses in QDPS.           40 7.5.6.2.13       Indication of Bypasses:    If one or more channels of the ESF qualified controllers have been deliberately rendered inoperable, this fact 49 will be continuously indicated on the QDPS display. If one or more channels of the SCWLCS subsystem has been deliberately rendered inoperable in the QDPS hardware, the action will result in the partial trip of the respective chan-nel.
7.5-9                    Amendment 49

ATTACHMEN STP FSAR     ST-HL AE l@T I PAGEI4 OF 8l i
: 2. Data acquisition and signal processing for the ESF Status Monitoring       l System.                                                                    ,
1
: 3. Data acquisition and signal processing for other normal plant monitoring   j systems including the plant annunciators and the plant computer.            -
7.5.7.1.1   System

== Description:==
The ERFDADS functions are performed by      {
several subsystems. Data acquisition is provided by multiplexers within the       l ERFDADS, the-QDPS (see Section 7.5.6), the Meteorological (ME ) System and #
the Radiation Monitoring System (RMS) (see Section 11.5         ). The ERF com-         /
puter-performs the required data processing. CRT devices     provide display in the control room (CR), Technical Support Center (TSC) and the o        A simpli-         X fied interconnection diagram of the ERFDADS is shown in Figure 7.5.7-        Q 7.5.7.1.1.1    Safety Parameter Display - The Safety Parameter Display System, as described in NUREG-0696 and NUREG-0737 Supplement 1, is implemented via the ERFDADS. The design of the ERFDADS is integrated with the implementa-tion of RG 1.97 (see Appendix 7B) and the Control Room Design Review (see Appendix 7A, Item I.D.1).
EOC.
The ERFDADS provides plant and environmental data to aid operators and manage-ment in the CR, TSC, and 0 to respond quickly to abnormal operating condi-               N tions and mitigate the consequences of an accident. The ERFDADS functions during normal operations and emergencies to provide the following services:           ,
[ 40
: 1. Provide plant and environmental data that is needed for the reactor oper- l ators to quickly assess the safety status of the plant.                        j.
: 2. Allow technical personnel access to comprehensive plant data, enabling them to assist operators without adding to the number of personnel in the control room.
: 3. Provide reliable plant data to the CR, TSC, and EO
: 4. Aid the operators in the detection of abnormal operating conditions.
: 5. Assist in the identification of the causes leading to any abnormal-ities.
: 6. Monitor plant response to corrective actions.
: 7. Providegroupingofparameterstoenhancetheoperators)abilitytoassess plant status quickly without surveying all control room displays.
: 8. Provide human factors engineered display formats (simple and consistent display patterns and coding).
: 9. Provide display information on a real time basis, along with validation of data and functional comparison capability.
7.5-10a                  Amendment 49

ATTACHMEN i ST-HL-AE- N STP FSAR            PAGE lo OF fl
: 10. Provide display information on a real time basis for monitoring the RG 1.97 variables, as defined in Section 7.5.1 and Appendix 7B. These vari-ables are utilized to monitor the critical safety functions of:
Oberific4f;$                                                              l e     R::: d fi j -..m.1 ?
e     Reactor coolant system   inkpr   :trih :: ::;l e     Reacto'r coolant inventory :: : ;l       c e     Reactor core coolin8                                                   49 e     Heat sink maintenance e              /
Pr' TJ . _;;;; gontainment environment The bases for the parameter selection are presented in Appendix 7B.
t
                                                                                            )
7.5-10b                   Amendment 49

ATTACHMENT i ST HL-AE-gfD8g PAGE  S\
STP FSAR i
Table 7.5-1 identifies the specific parameters and indicates those available in the TSC and @ got,                                                                            )(
7.5.7.1.1.2     Data Acquisition and Signal Processing for ESF Status Monitoring - The ERFDADS performs data acquisition and signal processing for ESF h Status Monitoring System. Input to the ESF Status Monitoring System                        $
Ts via demultiplexers within the FRFDADS. The ESF Status Monitoring System is described in Section 7.5.4.                                                 -
7.5.7.i.1.3     Data Acquisition and Signal Processing for Other Normal Plant Monitoring Systems - The ERFDADS performs data acquisition and signal X
processing annunciator [for and other   normal the plant     plant monitoring computer.      Input tosystems  includin the plan         the plants annunciato       via          )(
[ERFDADSdemultiplexerj                                                perconf o f                 )(
7.5.7.1.2     Equipment

== Description:==
prouw C orarol Cc4 b$ntTy 7.5.7.1.2.1     Multiplex es (MUX) - Non; Class       multiplexers are utilized           X for data acquisition from field inputs, 'switchjearpnd relay racks for input                    X into the ERF computer. The multiplexers are located in the glectrical                           x guxiliaryguildingswitchhearroomsA,BandConelevations10',35'and                                    )(
60', 7 the relay room on elevation 35'; and the separation group D                               X distribution room on elevation 10'.
DMu d 7.5.7.1.2.2 Demultiplexer[(Non Class [E DMUXs are utilized to provide X input from the ERF computer to other ; plant monitoring systems including the ESF Monitoring System and the plant annunciators.
L (tatus,                                                                                   0 7.5.7.1.2.3 ERF Computer - The ERF computer portion of the ERFDADS is located in the TSC (EAB, elevation 72') and provides data to the control room, TSC,andQdisplaydevicesandoffsitedata] links.                                                      Y E OC-TheERFcomputerreceivesdataconsispingoftheRG1.97definedanalogand                                  Y digital variables and other va d La directly from the ERFDADS multiplexers.
QDPS, Meteorological System and RMS via redundant high speed data"9 1nks.                        X Su rple medati m Carmatim The ERF computer performs any data processing required beyond that performed by the data acquisition equipment. Redundant central processing units are provided with adequate memory capacity to support ERF data acquisition, management and transmission functions on a real time basis.
EOC.
7.5.7.1.2.4 Man Machine Interface - CRT display devices are located in the CR, TSC, and          to present ERFDADS information to operators and management in a concise, easily intelligible format.
The primary SPDS display page is dx.insn: or :: 1: art m contrci rccr display                    )(
d-'~       > ~ e TSC ?ispicy devi::. This dispicy is available on all ERFDADS display devices.                           g      gt e,,
7.5.7.1.2.5     HVAC Support -     AC, with sufficient reliability to support             /
the above ERFDADS availability requirements, discussed in Section 7.5.7.1.3, is provided in the TSC computer room.           ERFDADS equipment located outside the TSC computer room is designed to function in the normal design environment for the areas in which the equipment is located.
7.5-11                            Amendment 40

A 6 i ALHME  l ST HL-AE- i STP FSAR            PAGE yVOF }
f#
The TSC HVAC is further described in Section 9.4.1.
7.5.7.1.2.6 Power Supply - ERFDADS equipment including multiplexing          X cquipment, the ERF computer and its peripherals, di lay devices, and //0ad printers. "hich 2re 1cc2ted eith!" " prer birck ,p#a rovided with/J20 vac          X power from a dedicated non-Class IE uninterruptible power upply (UPS) capable of maintaining system operation for 2 hours and capable of maintaining system memory for 8 hours. Normal AC power to the UPS is provided from a non-Class 1E dianel generator-backed bus.                                       g$
* GOL ERFDADS equipment located within the           s provided with reliable 120 vac       I power from the      r diesel generator-backed bus.                                     X EOC-7.5.7.1 't System Operational Requirements: The ERFDADS data channels meet the 99 e . cent availability requirement defined in NUREG-0696 Section 1.5 under pressure and temperature conditions exceeding cold shutdown conditions.
The system meets an 80 percent availability requirement during plant cold shutdown condtions.                                                                   N t
Data processed through ERFDADS is qualitatively corparable with other Post Accident Monitoring System, Radiation Monitoring System, and QDPS data displayed in the CR with respect to accuracy and response time.
7.5.7.2 Analysis. The ERFDADS design insures that any failure or
:alfunction of the ERFDADS equipment beyond the Class IE isolation devices does not compromise any safety-related equipment, components, or structures.
A verification and validation plan is provided for the ERFDADS software to demonstrate conformance with the functional requirements of NUREG-0696 and         40 NUREG-0737. This plan provides for an independent review of the system coftware.
Isolation and separation of Class IE signals is provided in accordance with RG 1.75. Inputs to the ERFDADS are isolated at the exit point of the isolation devices (see Figures 7.0.3-1 and 7.5.7-1).                                              y 1.5.6 i This system is designed to meet the following criteria:
: 1. No single-point failure in any ERFDADS component has any effect on the plant operation. Any such failure is monitored in the CR. Redundant hardware is utilized when required to satisfy this requirement and to improve reliability.
: 2. Where redundant devices or assemblies are utilized, failure of one is detected and indicated to the ERF computer, and causes automatic transfer of functions to the other device or assembly without effect upon system performance.
: 3. On line diagnostic routines and transmission error checking provisions in the data network and host processora aid in maintaining validity of all data interchanges and in verification of the continuous functional integrity of system equipment.
t 7.5-12                       Amendment 40

fl al           o TABLE 2.5-1                                          j ho V        ,
POST ACCIDENT MONITORINC INSTRUMENTATION 2ndice tpoh Sensor Eoc 'b                               x Qualif Icat ton -")                       Control          Implemen-    Sensor  F#P       TSC     Conformance Type /     Environ- M             Number            Room             tation       Power    Indica- Indice- to RG     7 V etable             Range / Status M          mental         Selante of Channels                        Date         Supply   tion    , tion   Rev.              K Yes      I r ;'- -        @PS              Core Load    IE      Tes      bes      Note b            I RCS Fressure         0-3000 pats    Al.Bl.B2   Ten (rt'e Range)                        Cl.r2.D2                                             I recorded 0-700*F        Al.Bl.82   Yes            Ten      1 per loop       @PS              Core load    IE      Tes       Yes     Conforan            %
% tide Range                                                                                4 recorded                                                                  A T
RQ tidi Range            0-700*P        A1.Bl.52   Ten            Yes      I per loop       @PS              Core Load    IE      Tes       Yes     Conforms            /
T s %I-                                                                                  4 recorded                                                                g gand Wide Range Stess     0-100% of      A1.Bl.52   Yes            Ten      1 per steem      ODPS             Core Load    IE       Ten      Tes     Conforms C6nerator Level      span           D2                                 generator         4 recorded                                                                /(
WaTtf                                                                                                            Tes      Yes     Conforms Marrow Range Steam   0-100%         Al.Bl.B2   Yes            Yes      4 per steam       @PS             Core Load    IE Cenerato Level       of span        D2                                 generator        / recorded                                                                 )(
4W                                                                          ii ptr 5f-Prscourire Level      0-1002        A1.Bl.D2   Ten            Tes      4 ;- ;L g @PS                     Core Lead IE       Tes       Yes    Conforms           (
g of span                                                                I recorded                                                               )(
Containment 65
                         -5 to M peig   A1.Bl B2 Tes              Yes      4 g ;* ^ /@PS                     Core Lead     IE      Tes       Yes    Conforms    40    N   in Pregnare                           Cl.C2.D2                                             2 recorded                                                                   q r                                                                         3                                 Core load     IE                Yes    Conforms Y Stsamline              0-1400 pelg   A1.Bl .D2   Yes           Yes     -4=per loop        @PS                                   Yes                                )(  ta I per loop                                                                  N C Pensure recorded                                                                          -
Yes                        @PS             Core Load     I F. Tes       Yes    Conforms         E 0-1002         Al.Bl.D2   Ten R; fueling Water                                                       3 ;-                                                                                               ,
2 meters                                                               X    "Up Ststar.e Tan g str/ of span                                                          g K recorded Level Containment Water    0-609.000 gal  Al.Bl.82   Tes            Yes      3;    -    '-
                                                                                             @PS             Core Load     IE      Tes       Yes    Conforms         )(       fl Level (Wide Range)    (0-6 ft.)     C2.D2                                                1 recorded                                                                  hk      ;
Containment Water    Bottom of      AI.52.C2   Tes            Ten      2 --- '--         @PS             Core Load . IE       Tes       Yes    Conforms-        /    kr Level (Narrow        Samp to Top    D2                                                   2 recorded                                                                  3 I
Range)               of Sump                                                                                                               ,
Austilary Peed-      0-100% of     A1.Bl.D2   Ten            Yes      3---'---          @PS             Core Load     IE     Tes       Tes    Conforms        4 E water Storage           span                                                               I recorded S Tae Level                                                                                                                                                       g 3       V 1414U                                                                                                                            Yes    Note o                    ]
Austit'ary Feed-     9-t99t*       A1.81.D2    Tes           Yes      1 per loop            PS          Core Lead     IE     Tee                            )(
trter Flow           ar -p==                                                                recorded                                                         y i    4/5T                                                                                 4 .n,k3 o-7oo galp

TABLE 7.5-1                                                              .
POST ACCIDENT MONITOR 1NC TNSTRtMENTAff0N (Continued)                               I' # *
                                                                                                                                                                                  , s.
EO C,                             40 Sensor Qualification                        Control                  leptemen-   Senent   Jer"           TSC    Conformance Type /    Environ-             Number         Room                     tation      Power     indica- indles-      to RC t Range /S tatus                       Cateory   mental       Setaste of Channels    Display                  Date        Supply    tion          tion   Rev.h.97          N Tartable 2 ;-- ' -* / QDPS                       Core Load    IE       Tes L'
Yes O
Note e y
1Rpren                               A1.Bl.B2  Yes          Yes Kigh Range 2 meters
                                                                                                                                                                                                                  !'4 Containment          10 R/hr                              C2.E2 Radiation Level      Comma                                                                              2 recorded Steam Cenerator       '"_       !*                        A1.82.C   Yes          Yes     1per[ low-     COPS                     Core Load    IE       Yes           Yes    Conforme 4 meters Blowdown Radia-tion Level g  .1
[                                                        down[ine       4 recorded IA NC C-Steam 1tne Radia-     !"       " *"                       A1.52.C2  Yes          Tag     1 per stese QDPS                        Core Load    IE       Yes           Yes    Conforme tion Level                                                E2                             line           4 meters                                                                              Y gp* L , p"                                                                         4 recorded
                                                  , gc                                                                                                   .
100-2200*F                          A1.51.C1  Tea          Tes     2 trains of QDP f tAcr a Core Load                   1E       Yes           Yes    Conforme Core Exit Temperature                                                                              25 thermo-     H     and ** d                                                                     *e
           *'                                                                                                      couples each, f4erage .# hathsf equally dis- h rent                                             {
tributed       recorded meroes corehg                                                                                    40 grants)
RCS Subcooling        200*F sub-                          A1.51     Yes          Yes     2 r-    ' -
QOPS                     Core Load    1E       Yes           Yes    Conforme        )(
cooltas to                                                                        2 recorded 5044tP superheat                                                                                                                                                         K Meutron Flue          I d te 2001                         31.D2     Tee          Yes     2 r-    '-
QDPS                     Core Load    IE       Tee           Yes    Note r         K (E; tended R uge)    Full Power                                                                     g K recorded Neutron Fler          -0.5 to + 0                         31.02     Yes          Yes     2 -- ;'        QDPS                     Core Load    IE       Tee           Yes    Note r         )(
Secrtup' Rate         dpa                                                                             tT4 recorded ae Reactor Tessel       Upper Core                          Bl.C2.D2  Yes          Tee     2 ;:r ;'_- y ne=t%
QDPS               fle   Core Load     1E      Tes           Yes    Conforme       X water Level           Support Plate                                                                      gMd                                                              ,
y to top of vessel contatament           Open/ Closed                        C2.D2     Yes          Ten      1 per valve    1 pair of               Core Load     1E      Tee      ,,   Ye's   Note c Itzhts per
{a           Isolation Valve Sectus                                                                                                 valve                                                -
a           containment          0-101                                Bl.C1     Tee         Yes      2 p;r %
Y 00PS                      Core Load    1E      Yes           Yes    Conforme       y
              "                                                                                                                    1 recorded                                                                       ['
Hydrogen             Concentration
                $          Concentration ATTACHMENT /
ST-HL-AE- Inb PAGE -W OF &

Tant.E 7.5-1 POST ACCIDENT HONITORING INSTRUNFNTATION (Continued)
Sensor QualifIcatton                       Control        Implemen-   Sensor EOP      YSC ~    Conformance Type /    Environ-             Number         Room          tation      Power   Indica- Indica- to RC 1.97, V rtabl9                                 Range / Status Catepry   mental       Setsmic of Channels   Display        Date        Supply  tion     tioh    Rev. 82
,            Contral Rod                              Rods on        D3        No           No      I per rod     LFD            Core Load   N-lE   Yes      Yes      Conforms Position                                 Rottom Indtection                                                                                                                                              (Note z)
Contcineent                               0-180 pass     C1.C2     Yes          Yes     2 --- ' - # @PS              Core Load   IE     Yes      Yes Prx surs                                                                                               I recorded Conforms           [
(E2 tended Range)
RCS Prscoure                              0-3500 patg    AI.RI Cl  Yes          Yes     2 -- '--* Y QDPS             Core Load   IE     Yes      Yes      Note b (Extendid Range)                                                                                    2 recorded                                                             K Primary Coolant                            N/A            C3        No           No      1 post        CRT (ERF1) ADS) Core Load N/A     Yes      Yes      Notes d, h Activity and                                                                            accident Sampling                                                                                sampling system W W
(Note a)       C2,E2     Yes          No      1 --- '- -                  Core Load Unit Vent "
Radici%m CRT (RNS)                 N-lE    Yes      Yes      Conforms        X     m (Note a, v)           N Lent 40        g Puel Kandling                               -6     -l                                                                                                                           N IWol0ay        C2,E2     Yes          Yes     2 --- '- " QDPS             Core Load   IE      Yes      Yes     Conforms         )(
Bldg. Radiation                           uC1/cc                                                      2 meters                                                      g Levelk g g g                                                                                           2 recorded                                                         T Adjacent ButIdtng                           10hol0         C3        No           No      5 -- ' - M CRT (RNS)        Core Load   N-lE Arve Radiation Level mR/hr Yes      Yes     No e /          -[
Sits Environmental N/A                                     C 3,E3    No           No      N/A           Portable      Core Load   N-lE    No       No      Cor. forms          "U Radtstion Level                                                                                         Sampling (P.>rttble Monitoring) m Pramm rtser PORY                            Open/ Closed   52.D2     Yes          Yes     1 per valve   1 pair of     Core Load   IE      Yes      Yes     Conforms               m Settus                                                                                                  lights per valve
                                                                                                                                                                   =
gm y
( Preseartzer PORY                                    Open/ Closed   D2        Yes          Yes     I per valve   I pair of     Core Load   IE      Yes      Yes     Conforms             %_., ~
  , Ricck Valve Status                                                                                            lights per valve

1-F J
d YARLE 7.5-1 POST ACCIDENT MONITORINC INSTRIMENTATION (Continued) t..
Sensor                                    -
Control       implemen-      Sensor    EOF      TSC      Conformance Qualtitcation                                                                    Indica- Indica- to RC 1.97, Type /   Environ-~              Numher            Room          tation         Power Ranae/ Status       Cateory  mental       Seismic   of Channels       Display       Date           Supply    tion    Itton   - Rev . #2 V'rtable Yes       I per valve       ! Alarm       Core Load      N-lE      Yes      Yes      Conforms Prssaurtzer Safety open/ Closed          82.D2    Yes                                                                                                                    -
CRT (ERFDADS)
Valve Status                                              #
Yes          Yes       I per bank        I pair of     Core Load      IE        Yes      Yes      Note e Precourtser Hester   Open/ Closed        D2 lights per Brsaker Position                                                                           bank
                                                                                       '---                  Core Lead      IE        Yes       Yes    ' Conforms'     X Prw oortaer          1700-2500           14 2     Yes          Yes       4 --              QDPS
                                                                                               $ rtterdtd                                                               )t Pressure             pets D2       No           No         1 per pump        I pair of    Core" Load     N-lE      Yes       Yes'     Conferms RCP Status           On/Off lights per pump No         I per valve       1 ight per    Core Load     N-lE       Yes      Yes      Conforms     )L Pressurtter Spray    Open/ Closed        D2        No                                                                                                             M V !ve Statu,                                                                                   alve D2       Yes         Yes        1 --- '- F QDTS                 Core 1. cad    IE        Yes      Yes      Conforms    y          ,
Charging             0-500 m         g Flow                                                                                                                                                           40 y
Core Load      M-lE      Yes      Ves      Conforms    X Litdown Flow        0-500 ppm.      g D2          Yes          Yes       1 pr ;'_ ^         l meter
-                                                                                                                                                                    i vslume Contial       0-100%              D2       Yes          Yes       2 ;- ;'- # 1 meter              Core Load      IE        Yes      Yes      Conforms X
of span k O(8 TcnkLevel)Ideitf                         D2       Yes          isolation 1 per valve        I pair of    Core Load      IE/4-lE   Yes      Yes      Conforms CVCS Valve Status    Open/ Closed                                                                                                                   (Note f)
Valves                        11ghts per                                                               g valve                                                                     by only
                                                                                                                                                                           &r D2       Yes          Yes       ?,      ;!          I pair of   Core Load       IE       Yes      Yes      Conforms     K    M --h Chcratng Pump        on/ Oft                                                                                                                         (Note f)         >' )= I 1pegwp             lights per Status                                                                                       pump D, E Yes         Yes        2      r--
                                                                                             <    1 pair of   Core Load       IE       Yes       Yes     Conforms     x    %9 M
y Roric Acid           On/Off              D2                                 r                                                                *
(Note f)         g0 g g'ge pom p      lights per                                                          y Status     %
Trrnsfer(Pump   h Yes        1 per loop pump QDPS        Core Load       IE       Yes       Yes     Conforms     K RCP Seal            0-20 apa.        - D2         Yes M                                                        4 recorded                                              (Note f) g Injection Flow e
E E
g                                                         -

YARI.F. 7.5-1 POSY ACCIDFNT MONITORING INSYRtMFNTAY10N (Continued) t..
Sensor Qualtitcation                        Control         Implemen-   Sensor   EOF      TS''      Conformance Indica , Indica- to Rc I 97 Type /   t'nviron-            Number         Room            tation      Fower V'rfahle          Ranae/ Status   Cattory  mental-      Setssic of Channels    Display         Date        _ Supply tion    'tlon    ' Rev. #2 SC Atmospheric    0-1002 Open     D2.E2    Yes          Yes     1 per valve QDPS               Core Load   IE       Yes      Yes       Conforms FOR7 Status                                                                    I meter per valve                                                                        .
Main Steamline    Open/ Closed    B2.D2    Yes          Yes     1 per valve    I pair of       Core Load   IE       Yes      Yes       Conforms Isolation Valve                                                                lights per                                              (Note f)
Stttua                                                                         valve M2ia Stesaline    Open/Clased     R2.D2    Yes          Yes     I per valve    1 pair of       Core Load   IE       Yes      Yes       Conforma RypIns Valve                                                                   lights per                                              (Note ()
Status                                                                         valve SC Safety Valve   Open/ Closed    D2 E2    Yen          Yes     1 per valve Alarm              Core f. cad N-lE     Yes      Yes       Conforms Status                                                                         CRY (FRFDADS)                                  .
M;ta Feedwater    Open/ Closed    D2       Yen          Yes     1 per valve CRT (FRIY) ADS) Core Load      IE       Yes      Yes       Conforms         )(
Centrol Valve                                                                                                                          (Not g . )
Stttus 40         ,
y Mata Feedwater     Open/ Closed    D2       Yes          Yen     1 per valve CRT (FRFDADS) Core 1. cad      IE       Yes      Yes       Conforms /             y y Cortrol Bypass                                                                                                                          (Note Q Q)
I      y 3 Vcive Status                                                                                                                                                   g M2in Feedwater    Open/ Cloned    D2       Yes          Yes     I per valve    1 pair of     ' Complete    I F. Yes      Yes       Conforms isolation Valve                                                                lights per                                              (Note f)       M Status                                                                         valve DHH Main Feedwater Open/ Closed    D2       Yes          Yes     I per valve    I pair of       Complete    IE       Yes       Yes      Confor=*
(Note f)
X oiH Isolation '' '-
BypIss Valve lights per valve Mr -h Yg Status                        t                                                                                                                            drrig
                        ,5.oxso,sy4, o m Mitn Feedwater    44405           D2       Yes          Yes     3 per loop     QCFS            Core Load   IE       Yes       Yes      Conforms       )( M 7C Flow              ed-eyes                                                      I per loop recorded
                                                                                                                                   ,                          w(
SC Blowdown       open/ Closed    D2       Yes          Yes     I per valve    I pair of       Complete    IE       Yes       Yes      Conforms Irelation Valve                                                                lights per                                              (Note f) valve
{Statua u
Open/ Closed    02       Yes          Yes     I per valve    I pair of       Complete    IE       Yes      Yes       Conforms
{SCBlowdown a Sample [ Isolation                                                                                                                      (Note ()
lights per                                                                           j
{ValveStatus                                                                      valve                                                                )(
O

YAPIF. 7.5 1 b's FnSY ACCIDENT MONITORINC INSTRt'MENTAYlON (Continued) al i.
Sensnr Qualification                       Control         implemen- Sennor  EOF      TSC      Conformance Type /   Environ.             Number        Rons            tation    Power   Indica- Indica- to RC 1.97 Vrriebte              Rense/ States     Catenry  mental       Setsste of Channeln   Di= play        Date      Supply  tion    atton   , R ev ., f2 L
M HMSI Flow            0-2000 gal / min  D2       Yes          Yen     2 per 51      6 metern       Core Load  N-I F. Yes      Yes      Conforms Y
pump (gut lag
                               ..                                            w4 W LHSI Flow     0-       al/ min  D2       Yes          Yen     2 per SI      6 meters        Core Load N-I F. Yes      Yes      Conforms     W M SO                                         pump (hmtb s c.4 kg)t s- ogial/mu'a FCCS Accumulator      0-7    pafgN      D2       Yes          Yes     2 per tank    6 metern        Care Load N-lE    Yes      Yes      Conforms Fransure A stilary Teed-       Open/ Closed      D2       Yes          Yes     I per valve    I pair of      Core Load I F. Yen      Yes      Conforms water Valve Status                                                                   lights per                                         (Note f) valve Containment Spray     0-1001            D2       Yes          Yes     I per train    1 metern       Complete  N-I F. Yes      Yen      Conforms Finw                  of span                                                                                                                       40 we C4ntainment Spray     Open/ Closed      D2       Yes          Yen     I per valve    I pair of      Complete  IE      Yes      Yes      Conforms            y
. System Valve                                                                         lights per                                         (Note 1)            .,,
[cmStatum                                                                                valve                                                                   g Containment Spray     on/Off            D2       Yes          Yes     I per pump     i pair of      Complete  IE      Yes      Yes      Conforma Fumgtatus                                                                            lights per                                         (Note f)     X pump M met W.M  Fan Cooler                                 Yes          Yen     1 per fan      1 A ara per    Core Lead IE/M-lE Yes      Yes      Note a       N 3-4 in, water gf,D2 Differential          On/Off                                                         fan Pretnure/Ststun
                .                                                                train QDf$                                                                 hh-4 CCW Pump Discharge    0-150 pelg        D2       Yes          Yen     1 per headma '       .-       Core Load IE      Yes      Yes      Conforms            -4 M --
Frannure                                                                                                                                (Note 1)       Or*h r
V9l%                                                                      d >riI r g.,
containment Vent-     Dren/ Closed      D2       Yes          Yen     I per dampas. I pair of       Core Lned IE      Yes      Yes      Conforma    Y i1.1ttonammmar.Yehpg                                                                1tahts per                                                     X  Om Statun 50 dampee-Yelv t t rain nors X  MM xe CCW Header           %-250'r            D2       Yen          ten     1 per headas   '--n           Core Load IF. Yes      Yes      Jonforms    X  -
Yamperature QDFS N CCW Surge Yan          0-100% of                                                                     Core Load IE      Yes      Yes      Conforms npan D2       Yes          Yen     I per tank cowpartment                                                       (Note f)    [
{l.evel          gg a
s

YARLF 7.5-1 POST ACCIDENT W1NTYORING INSYRifMFNYAYION (Continued)
Sensnr Qualtflestion                             Control     Implemen-   Sengor    F0F         TSC      Conformance Type /   Fnviron-                   Number        Room        tation      Power     I r.d tc a- Indien- to RC l.97, V rt'ble                 Ranae/ Status      Caterry  mental       Seismic       of Channels   Dis la      Dare        Supply    tion        t t'on   Rev. #2 affr*rrietsgs)   n                                                40 Yes          Yen           I per ESF     "
Core Load   IE        Yes         Yes      Conforma CCW Flow to F.SF         0- N               D2 Compon;nta              y for                                                                 M-component,heuc/e composenT[4(ader                                        1 y C(w                               IE        Yes         Yes      Conforms CCW Vzlve Status         Open/ Closed       D2       Yes          Yen           I per valve   I pair of   Core 1.oad lights per     *
(Note f) valve Scy                     s   repMt s.1]m                                                                           IE        Yes         Yes      Conforms
     'n :_          ' " ' -   0-          fov'   D2       Yes          Yes           1 per major ODPS          Core Load
           - ,_         Flow  opam. con 6penenT/                                     FSF component                                                        (Note f)
W sse t e temenT5          h ead#                                                                                                                    Conforms
          --'-! C!n           Open/ Closed       D2       Yes          Yen           1 per valve    1 pair of  Complete    IF/N-lE   Yes         Yes 44a=&aa.                     Ifghts per                                            (Note f)
Q. ^ = ECW Valva Status
                                                                                 "'s               valve er-W                            mete v-ESF Fnyironnent Temperature              Yemperature        D2       Yes          Yes           I per ESF      1 alarm    Core Load   N-lE      Yes         Yen      Conforma above metroint                                         component /                                                          (Note f) cubicle EsF CvMf.le,.                                                                                                                                                   40  a Yes          Yes            1 per ESF     1 pair of  Core Load    IE       Yes          Yes     Conforms Fsu/ Cooler            Fan Stopped /      D2 y
component /    lights per                                             (Note f)       M 6 Status                      Running cubicle        item                                                                  $
f,,,
e Yes         Yes            I per ime     1 meter or  Core 1.oad  IE/N-IF. Yes         Yes     Conforms Sttndby Power           Bus Specific       D2 tnd Emergency                                                                                 alarm for Power Source                                                                                  each power Statua                                                                                        nource                                                                gg
                                                                                                                                                                          > -t-4 Othrr Safety-           Component           D2       Yes         Yen            1 per source 1 meter or   Core 1.nad  IE/N-]E   Yes         Yes     Conforms (Note y)
Oi-4 Reittsd Energy          Specific                                                             alarm for                                                                I"*
Sourcen                                                                                      each power                                                                   .I source                                                                       K Yes          Yes           1 per heat    QDPS        Core Load   IE        Yes         Yes
* Conforms RHR Heat Exchanger      50-400'F           D2 Dischtrge                                                                      enchanger     3 recorded                                                           3,0 Temperature                          g Yes          Yen           1 per DMP                 Core 1.oad   IE       Yes         Yes      Conforms RitR Flow               %N                 D2                                                QDPS span                                                   train          3 metern k
E.
2 E
I s

m TARIE 7.5 1 POST ACCIDFNT MONITORINC INSTRUMENTATION (Continued)
Sengor Oualification              .
Control       Implemen-  Sensor   EOF     TSC      Conformance Type /    Fnviron-              Number          Room          tation     Power    Indica- Indica- to RC 1.97 Vr r is hle          Ranae/ Status Cateory   mental      Setsste   of Channels     Display       Date       Supply   tion    t' ton   Rev. f2 Open/ Closed  D2        Yes         Ye         I per valve     I pair of    Core Load  IF N-lF. Yen     Yes      Conforms RHR Valve Status                                                                                                                      (Note f) is                       lights per tion Valves               valve Iv)
QOr$
Rxctar Trip          open/ Closed  D2        Yes         Yes        I per brenner 1 pair ,of     Complete   IE       Yes     Yes      Conforms Brsaker Position                                                                    ll Rh ts per                                      (Note f) breaber Open/ Closed  D2        Yes         No         I per valve     1 pair of    Complete   N-lE     Yes     Yes      Conforma Turbine Covernor Valve Position                                                                      lights per                                        (Notes f.z) valve Open/ Closed  D2        Yes         No         I per valve     1 pair of    Complete   N-IF. Yes      Yen     Conforms Turbine Stop Valve Position                                                                      lights per                                        (Notes f.s) valve                                                         40 Yes         Yen        1 per pump      1 pair of    Core Load  IE       Yes      Yes     Conforms Noter-Driven         On/Off        D2 U
Auxtllary Feed-                                                                     Ilghts per                                        (Note f)         '
w   witer    Pump Status                                                                pump p.mp dialmy, g o r$                                                             3
                            %00 f 5s g                       Yes        I sasMaa.                    Ccre 1.oad  IE      Yes      Yes     Conforms         $
w Arztllary Feed-        0-56MN>-eye   D2        Yes                                    I meter.
wIter Turbine        Open/ Closed                                   assad pots 5prt I pair of                                         (Note f)
Pump Status                                                         indicator. lights per 1 per steam    valve inlet valve St Pump Status       On/Off       D2        Yes          Yen        1 per pump     1 pair of    Complete    IE      Yes      Yes     Conforms       h   -4 (Note f) lights per Pump tjo St Valve Statum      Open/ Closed D2         Yes         Yen        1 per valve    1 pair of    Complete    IE      Yes      Yes     Conforms          .E J
Ilghts per                                        (Note ()      O,3 CZ valve                                           ,
y                                                                                                                                                      ':4  S Yen         Yen        1 per pump      1 pair of    Complete   IE      Yes      Yes     Conforma       -
F-asential Cooling   On/Off        D2 a,
rs Water Pump Statum                                                                   !!Rh tm per                                       (Note f) pump f
on/Off        D2        Yes         Yen        1 per pump      1 pair of    Complete   IE       Yes     Yes     Conforan gCCW Pump Featus                                                                                                                         (Note f) lights per pump l

m TARI.E 7.5-1 POST ACCIDENT MONITORING INSTRUMENTATION (Continued) r.,
Sennor Qualification                         Control       Implemen-   Sensor EOP      - TSC     Conformance Type /    Environ-
* Number          Room          tation      Power   Indica- Indica- to RC 1.97 Vsrlable             Ranae/ Status    Cateory   mental      Seismic of Channels     Display       Date        Supply tion       tion    Jtev. f2 RHR Pump Status      On/Off           D2        Yes         Yes     1 per pump      1 pair of     Complete    IE     Yes        Yes     Conforms lights per                                           (Note f) pump a(TAten St Actuation         On/Off           D2        Yes         Yes     I per p&ame. I Alarm       Core Load   IE     Yes        Yes     Conforme       y Status                                                              -tygm aftu @ a Castsineent Iso-     On/Off           D2       'Yes         Yes     I per p&ame. 1 Alarm       Core I. cad IE     Yes        Yes     Conforms
       !stion Actuatton                                                     tyain                                                                             K Status Control Room         10 I
E3                                        #
to                   No          No      1 -- ;'         CRT (RMS)     Core Load   N-lE   Yes        Yes     Note 1 RsdistionLfAh        10{mR/hrhete) 10~   to 10'I    E2        Yes        Yes      2 p w M QPDS                  Core Load   IE     Yes        Yes     Conforms       X uC1/cc(tdal(gg,}                                               2 meters 2 recorded                                                         )f Access Area          10'   to         E3        Yes        No       I per           CRT (RMS)     Core Load   N-lE   Yes        Yes     Note 1 RIdiation            10 R/hr                                        designated                                                                      40 p                                                                      area                                                                                      y Condenser vacuum     10~   to         E3        Yes        No       I 7--    '-
CRT (RMS)     Core load   N-lE   Yes        Yes     Note n                5
    ~ rump Radiation        10 uCl/cc                                                                                                                                $
Level Concentration from Lfquid Pathways                                  -
g(f3y
                                                                                                                                                                 > -4 SC Blowdown      10    to         E2        Yes        No       I per plant     CRT (RMS)    Core Load    N-lE   Yes       Yes      Note t 10 uCt/cc d>O C[I cond. Polish     10    to         E2        Yes        No       1 per plant     CRT (RMS)    Core Lnad    N-lE   Yes       Yes      Note t                N m 10' uC1/cc 1
                               -h
                                                                                                                                           .                     O2 ri C M
2 1.fquid Radwaste 10    to         E2        Yes        No       i per plant     CRT (RMS)    Core Load    N-lE   Yes       Yes      Note t            30 g
10'y uCi/cc                                                                                                                          '_
e E. TCB Drafn        10    to         E7        Yes        Nc,      I per plant     CRT (RMS)    Core Load    N-1E   Yes       Yes      Note t
                               ~I W                       10    uCf /cc                                                                                                         _
f.
8 l

m TABt.E 7.5-1 POST ACCIDENT MONITORING INSTRUMfNTATION (Continued)
Sensor Qualification                           Control        implemen-  Sensor EOF     TSC      Conformance Number             Room          tation     Power  Indica- Indica- to RC 1.97, Type /    Environ-Cateory   mental      Sstemic of Channele        Diaslay       Date       Supply tion     tion    Rev. #2 i    V rf<ble               Ranae/ Status Effluent Fath Flow Rate / Status __                  --
No          No      1 per plant CRT (RMS)            Core Load  N-1E   Tes      Yes     Note q SC Blowdown      0-1001        E3 Flow           of span l
Tes                 1 per valve        1 pair of     Core Load  N-1E   Yes      Yes     Notes q, w Valve Status Open/ Closed    E2                    No Ifghts per 1
valve No      1 per plant CRT (RMS)            Core Load  M-1E   Tee      Yes     Note q cond. Polish     0-100%        E3        No Flow          of span 1 per valve         1 pair of     Core Load M-1E   Tes      Yes     Notes q, w valve Status Open/ Closed    E2        Yes         No j
lights per valve       _
40 No       1 7--
                                                                                        # CRT (RMS)       Core Load N-1E   Yes      Yes     Note q Liquid Redweste 0-1001          E3       No Flow          of span Tes        no       1 per valve        1 pair of     Core Load N-1E   Tes      Yes     Notes q. w          h 4  ?          Valve Status Open/ Closed    E2                                                                                                                     ,
lights per y                                                                                        valve                                                               g
,  y No      1 per plant CRT (RMS)            Core Load N-1E    Yes     Yes     Notes q TCB Drain         0-1001        E3        No Flow           of span Valve Status Open/ Closed    E2        Yes         No      1 per plant        CRT (ERFDADS) Core Lead  M-1E   Teo      Ten     Notes q. w       gy
                                                                                                                                                              > ~f-4 EtCOADs Unit vent        0-100%        E2        Yee         No      1 per ;'        ' CRT p          Core Load  M-1E   Tes      Yes     Note w QI"i j C~o 3
Flow          of span                                                                                                                            DI Condenser        0-100%        E3        No          No      1 --- *--* # M (RMS)             Core Load  N-1E   Tes      Yes     Note v           NE O
vac e Pump       of span g
k,          Pump Status   on/off        E2        Yes         No he Pomp 1 ; - '--* # CRT (ERFDADS) Core Load       N-1E   Tee      Yes Notes v. w V
[*
['
No       15p ;?r' CRT (ERFDADS) Core Load           M-1E   Teo      Yes     Note u Netsorological        4/4-           E3       No P.r..et.ra          < _a
: 2. sm) 1

_                                                 .            o                      .
7
                        -                                                            O                                                              C t
t
                                                                                                                                                                       ?
TABLE 7.$-1                                                                               I POST ACCIDENT WONITORINC INSTRt19tENTAT10N (Continued)                        .
O Sensor                                                                ggc Qualification                           Control        implemen- Sensor Ber     TSC      Conformance Typef       Environ-              Number        ' Room           tation    Powar  Indica- Indice- to RC 1.97, V*rt'ble         Renae/ Status Cateory     mental      Setemic of Chas.nela      Display        Date      Supply tion    tion     Rev. M h
Contsineent Sump N/A           E3          No          No        1 post          CRT (ERFDADS) Core Load  M-1E   Yes     Yes      Notes d. h I        cnd Atmospheric                                                  accident Sampling                                                         sampling sys-4                                                                         Lem 6 .- p:_..; '
Roric Acid Tank                                                                                                  --
Note 3 Charging Flow C;.ntainment                                                                                              --                      Note 1 Atmo:pheric Temperature f
l Accumulator                                            --                                                                         Note j      40 Tx k Level i
Containment      --                                                                                                               Note k Sump Water Temperature                                                                                                                                          .
7                                                                                                                                                       N u  H ut Removal by                                                                                                                   Note m             ,
I
        ++ th3 Containment                                                                                                                                            ll.
F a Heat Removal                                                                                                                                     "N ty tem Emergency        --                        --                                                   --                                Note y Vsat11stion Damper Position O
      -                                                                                                                                                     m >
                                                                                                                                                            )>OI      t i
E     .
Om
* uZ        ,-
oo-4 M-i 1
2 3
8 l
I

(
ATTACHME         I STP FSAR           ST-HL-AE-PAGE 4)       M TABLE 7.5-1 (Continued) g        NOTES (10                           -11
: a. Noble Gas: 10      to       1/ce, Particulate:   10     to10/.lCi/ce, 2
X Halogens *: 10     to       1/cc.
To cover the required range of yarticulates and halogens, a cbmbination of on-line detection and grab sample capability with onsite analysis is em-ployed. These monitors are environmentally qualified, but not seismically qualified, since they are attached to a non-seismic system.
: b. .RCS Pressure - one qualified channel of wide range RCS pressure and two qualified channels of extended range RCS pressure are used to monitor RCS Pressure for STP.                                y
: c. Containment Isolation Valve Status - TP has identified inst mentation that is necessary to assess the pro ess of accomplishing or aintaining critical safety functions. The er tical safety functions efined are equivalent to those utilize'd in t     Westinghouse Owners       oup Emergency Response Guidelines, i.e. , R::: tin it~ C:ntr:1, RCS Pr :: r Cent :1, Reactor Coolant Inventory C:6:1, Reactor Core Cooling, Heat Sink                f Maintenance, and R: $ r Containment Environment. Containment isolation f(
valve status is not a critical safety function. However, the containment (solation valve positions were designated variables for monitoring the actual gross breach of the containment and are therefore qualified to
_ . _        , category 2 criteria.                                                          40 )(
: d. The STP Pos        ident Sampling System is sufficient for obtaining samples       N to perform detailed analysis of RCS coolant, containment sump, and con-tainment atmospheric activity. Offline measurement systems are considered Category 3 variables.
: e. Pressurizer Heater Status - RG 1.97, Rev. 2 specified that heater current was the preferred parameter for determining heater status. For STP, heater breaker position was selected for determining pressurizer. heater status due to hardware considerations. Breaker position provides adequate indication to the operator to ensure that the two pressurizer heater banks powered from the Class lE busses are operable.
: f. The study performed on STP indicated that these' parameters were in:1:f:3 seeAnd  y in the minimum set of parameters necessary to monitor the performance of:
: 1. Plant safety systems employed for mitigating the consequences of an accident and subsequent plant recovery to attain a safe shutdown condition, including verification of the automatic actuation of safety systems.
: 2. Systems normally employed for attaining a cold shutdown condition,
: g. Boric Acid Tank Charging Flow - For monitoring the performance of the
          }      Emergency _ Core Cooling System (ECCS), STP has designated Refueling Water Storage (RWST) Tank Level, High ead Safety Injection (HHSI) Flow,                f(
7.5-24                     Amendment 40

r.. _ ,_....;_ _ _ _ _ --_
ATTACHME         I ST-HL-AE- i STP FSAR               PAGE % 0 TABLE 7.5-1 (Continued)
           ~
NOTES Low Head ' Safety (LHSI) Injection Flow, Containment Water Level, and ECCS                  [
Valve Status. Since the ECCS does not take suction from the Boric Acid Tank (BAT), the Boric Acid Charging Flow was not designated a~ key vari-able. If the operator uses the BAT for boration following an accident, normal charging flow and RCS sampling is used to demonstrate that the RCS                                  '
is being borated.
: h. Data entry is via manual keyboard.
: i. Conte.inment Atmospheric Temperature - The WOG Emergency Response Guidelines (ERG) do not require the operator to take an action hat would result in adverse consequences if the Containment temperature was iedt tr-                      F pvw.by,,eeting an erroneous value. As such, the Containment temperature indi-                                y        ,
v    cation is considered a D3 parameter and is not specifically identified on this listing.                -
: j. Accumulator pressure indication and valve position indication for the accumulator discharge isolation valves and accumulator vent valves provide adequate status of the accumulators.
: k. Containment sump water temperature indication is not utilized by the operator to take corrective action. Other parameters were designated as                     40 O
           -              STP type D variables to demonstrate that the Safety Injection System (SIS) is operating properly when taking suction from the Contabnent sump.
: 1. Conforms to RG 1.97, Rev. 3.
: m. Heat removal by the Containment Heat Removal System (CHRS) - Other para-meters were designated as STP type D variables to demonstrate that the containment heat removal systems are operating properly. These include the following:
e Containment Spray Flow
!                         e       Containment Spray System (CSS) valve status e Containment Pressure e Containment Water Level e       Containment Spray Pump Status e       Reactor Containment Fan Cooler (RCFC) Differential Pressure e RCFC Status l                    n. Condenser Vacuum Pump Radiation Monitor - This parameter is considered to be a backup variable for the measurement of secondary side radiation.
l 7.5-25                                  Amendment 40

p-. . a .o _ . s.w -             a    --    - - - _ . .        .q r-                   --
ATTACHM      i ST-HL AE-   0 STP FSAR PAGE % OF 9l
    , .                                        TABLE 7.5-1 (Continued)
    *-                                                      NOTES Main steamline radiation monitors are adequate to provide primary indica-
                   -tion of this information. The condenser vacuum pump radiation monitor is anyironmentally qualified, but not seismically qualified, since it is attached to a non-seismic system,
: o. The STP design utilizes our physically separate auxiliary feedwater lines. The four Class lE transmitters provide the redundancy required.                U The requirement is to ensure flow to at least one intact steam generator post-accident. The required redundancy with a four loop plant is provided by one channel per     oop. SG                                                   4 4
tom kN % (o-           p-d is dbgel , J;qWide kpd vi"Range
                                                                      -tt- Gprovides DPS.
a diverse backup.
: p. Emergency Ventilation Damper Position - As an alternate to monitadng ventilation damper position, STP monitors radiogas, radioparticulate, j,g ---- End/or radiM concentrations at various locations in the plant which                    '/,
        ,F I           provide information concerning the status of the ventilation system.
These parameters include:
e     Area radiation in locations which contain, or could contain, sig-nificant quantities of radioactive material e     Unit vent radiogas concentration e     Radiogas concentration discharged from non-headered vents e     Environs radiation e     Fuel handling building vent radiation e     Effluent path flow rate
: q. Effluent Path Flow Rate / Status - Variables which provide the operator with information to estimate the magnitude of release of radioactive materials through identified pathways. Valve status is the primary variable and flow rate is a backup variable.
8-
: r. Neutron Flux - No diverse variable is required since the failure of one channel vill not cause the operator to violate the required safety fun-etion.
: s. Two Cont,inment high range monitors meet the requirements of a Type A variable. These monitors are Class IE, redundant and fully qualified to                %
Category I requirements.       Six area monitors are located throughout Containment with the range of 0.1 to 10,000 mR/hr that provide additional monitoring over this range.         In addition, the off-scale high readings of the low range monitors provide some information to resolve ambiguity above this range. These two qualified high range radiation monitors also satis-fy the requirements of NUREG-0737.
        'i 7.5-26                           Amendment 40

f
                                                                                           =     {
ATTACHMENT I ST-HL AE- l'IsD PAGE M OF TI STP FSAR TABLE 7.5-1 (Continued)
NOTES
: t. The study performed on STP indicated that these parameters were included in the minimum set of parameters necessary to monitor for release of radioactivity via liquid effluent pathways. These monitors are environ-mintally qualified, but not seismically qualified since they are attached to non-seismically qualified systems.
: u. Meets requirements of RG 1.23.
: v. For the purpose of radiological release calculations, the conservative          ,
ass'umption of maximum flow will be utilized. Actual flow indication serves as a backup parameter and is designated Category 3.
: w. These Category 2 sensors are environmentally, but not seismically qual-     40 ified, since they are attached to a non-seismic system.
: x. Rod position indication is provided in the CR via the digital rod position indication system light emitting diode (LED) display.
: y. Instrument loops on Class 1E systems are qualified up to and including channel isolation devices.
: z. These Category 2 sensors are environmentally and seismically qualified;
(            however, they are installed in a non-seismic system and are therefore not listed as seismically qualified instruments. They are installed using mountingssimilartothoseusedforcomparablgseismicallyqualified equipment.
X' I
l 7.5-27                   Amendment 40             l

                                                                                                                                        / r bg cM d TARLE 7.5-2 (f &% lytvfW ' 6& E                             rc, MAIN CONTROL BOARD INDICATORS AND/OR RECORDERS AVAll.ABLE TO THE OPERATOR CONDITION IV EVLNTS No. of Channels                                Accuracy Parameter                   Available     Required      Range                  Required        _
Indicator / Recorder          P'urp   e
: 1. Containment                     2            1          0-Il5% of design       +10% of full          Both channels indicated;       onttor post-LOCA Containment Press A                                                 pressure               scale                 ! recorded                    conditions N.
: 3. Refuteing Water ' -                          1          0-100% of span         +3% of level          Both channels indic       d;  Ensure that water is flowing Storage Tank              'N.                                                  upan                  1 recorded                    to the Safety Injection Sys-Water Level                       's                                                                                               tem after a LOCA; determine
                                                 ~                                                                                          when to shift from injection to recirculation mode
: 3. Steam Generator             1/SG             *          +7 to -5 ft from      110% of level          All    iannels indicated;     Detect SG tube rupture; mont-Water Level                                                om nominal full     span **               c . nnels used f or cont rol  tor SG water level following (narrow range)                                          10    level                                  are recorded                  a steam line break
: 6. Steam Generator
* 1/SG                        17 to -4    t from    120% of level          All channels recorded         Detect SG tube rupture; mon-Water Level                                             nominal fut    nad     spsn                                                tor SG water level following (wide range)                                           level                                                                      a steam line break
: 5. Steam Line                  2/ steam      1/ steam      0-1,300 psig          -
full scale  Both channels indicated;      Monitor steam line pressures y         Pressure                   line          line                                                       1/ steam line recorded        following SG tube rupture or
                                                                                                                                                                            ]
L                                                                                                                                           steam line break O                                                                                                                                                                           E
: 6. Pressurtzer                    2            1          Entire distane          Indicate that        Both channels indicated;      Indicate that water has re-     $
Water Level                                            between tap -           level is some-       1 recorded                    turned to the pressurizer where between                                       f ollowing cooldown af ter SG 0 and 100% of                                       tube rupture or steam line span ***                                           break
: 7. Containment                    2            1          102  to 100 mR/hr       15%                  Bot h chans   s indicated;    Monttor and indicate Hadiation Level                                                                                     I recorded                    radiation in containment          h [.-4 O
                                                                                                                                                         ,                      CO H. Containment                    2            2          O to 8%               15%                    Both indicated; I       orded Monitor and indicate hydro-       f 'k1 112 Concentration                                                                                                                 gen concent ration in Con-        %K tainment                          OE n .tZ
                                                                                                                                                  ,                       ,     M 3%
* One level channel per ' SG either wide or narrow range) with at least two wide-range channels for the plant.                                                        *
      ** For the steam brea      when t he water level chanr< 1 is exposed to a hostile environment , the accuracy required can be relaxed. The indicat        need con-g         vey to the opera r only that water level in t he SG is somewhere between the narrow-range SG water level taps.
h   *** Indicated     er level should be above the pressurizer heaters and below 100% of span (apprustmately 25% of span).
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L STP FSAR                     ATTACHMEN I Appsndix 7B                      h4           0 RI                 --l TABLE OF CONTENTS Chapter 7 Section       ,
1.pg.andix 7B                                         Page 7B.1       DISCUSSION                                                                            ,
7B.1-1
                       .7B.l.1     PLANNED VERSUS UNPLANNED OPERATOR ACTIONS                                               7B.1-2 7B.1.2     Variable Types                                                                          7B.1-2 4 f,,         7B.1.3     Design and Qualification Criteria                                                       7B.1-3 ie W 4                                                                                                                                    /
s**b/ "?"           7B.2       DEFINITION OF VARIABLE TYPES                                                            7B.2-1 7B.2.1     DEFINITIONS                                                                             7B.2-1 7B.2.1.1 Design Basis Accident Events                                                         7B.2-1 7B.2.1.2     Safe Shutdown (Hot Standby)                                                      7B.2-1 7B.2.1.3     Cold Shutdown                                                                    7B.2-1 7B.2.1.4     Controlled Condition                                                             7B.2-1 7B.2.1.5     Critical Safety Functions                                                        7B.2-1 7B.2.1.6     Immediately Accessible Information                                               7B.2-1 7B.2.1.7     Primary Information                                                              7B.2-1          40 7B.2.1.8- Key Variables                                                                       7B.2-2 7B.2.1.9 Backup Information                                                                   7B.2-2 7B.2.2     Variable Functions                                                                      7B.2-2 7B.2.2.1 Type A                                                                               7B.2-2 7B.2.2.2     Type B                                                                           7B.2-2 7B.2.2.3 Type C                                                                               7B.2-2 7B.2.2.4 Type D                                                                               7B.2-3 7B.2.2.5 Type E'                                                                              7B.2-3 7B.3        Criteria                                                                               7B.3-1 7B.3.1      General Requirements                                                                   7B.3-1 7B.3.2   -Equipment Design and Qualification Criteria                                              73.3-1 7B.3.2.1 Design and Qualification Criteria - Category 1                                       7B.3-1 7B.3.2.1.1 Selection Criteria - Category 1                                                    7B.3-1 7B.3.2.1.2 Qualification Criteria - Category 1                                                7B.3-1 7B.3.2.1.3 Design Criteria - Category 1                                                       7B.3-1 7B.3.2.1.4 Information Processing and Display Interface                                       7B.3-2 Criteria - Category 1 7B.3.2.2 Design and Qualification Criteria - Category 2                                       7B.3-3 7B.3.2.2.1 Selection Criteria - Category 2                                                    7B.3-3 7B.3.2.2.2 Qualification Criteria - Category 2                                                7B.3-3 7B.3.2.2.3 Design Criteria -- Category 2                                                      7B.3-3 7B.3.2.2.4 Information Processing and Display, Interface                                      7B.3-4 Criteria - Category 2 7B.3.2.3 Design and Qualification Criteria - Category 3                                       7B.3-4 7B.3.2.3.1 Selection Criteria - Category 3                                                    7B.3-4 7B.3.2.3.2 Qualification Criteria - Category 3                                                7B.3-4 7B.3.2.3.3 ' Design Criteria - Category 3                                                     7B.3-5 7B.3.2.3.4 Information Processing and Display, Interface                                      7B.3-5 4
Criteria - Category 3 7B.3.3       Extended Range Instrumentation Qualification                                     7B.3-5 Criteria I
7B-1                                          Amendment 40                     ;
I

T e
STP FSAR               ATTACHMENT I App 2ndix 7B              ST HL AE- 14fD PAGE WS OF #1 TABLE OF CONIENTS    (Continued)
Chapter 7 Appendix 7B                   Page Stetion Tcble 7B.3-1 Summary of Selection Criteria for                      7B.3-7 Category 1,2,3 versus Type A,B,C D.E                     .
Tcble 7B.3-2 Summary of Design, Qualification, and                   7B.3-8 Interface Requirements TYPE A VARIABLES 7B.4-1 7B.4 7B.4-1 7B.

==4.1    INTRODUCTION==

7B.4-2 Table 7B.4-1 Summary of Type A Variables 7B.5-1 73.5      TYPE B VARIABLES 7B.5-1 7B.

==5.1    INTRODUCTION==

7B.5-2 Table 7B.5.1 Summary of Type B Variables TYPE C VARIABLES 7B.6-1   40 7B.6 7B.6-1 7B.6.1    Introduction 7B.6-2 Table 73.6-1 Summary of Type C Variables TYPE D VARIABLE 7B.7-1 7B.7 7B.7-1 7B.7.1    Introduction 7B.7-3 Table 7B.7-1 Summary of D 7ariables 7B.8-1 7B.8      TYPE E VARIABLES 7B.8-1 7B.8.1    Introduction                                               7B.8-2 Table 7B.8-1 Summary of Type E Variables Table 7B.9-1       !!) f V ri:51: : d C:te; crier - Cr :                  -!
                  " fer re: Lieting of Veri:ble: ef Typ: ^ " C,D,E r!!b C2te; cry
                                                  !,' 3 l-l                                                       7".10 1 Table 7B.be-E NUREG-0737 Conformance Nova to pay 73.i belo        73,g. 3 7B-il                  Amendrent 40

E STP FSAR                         i Apptndix 7B            ATTACHMg@g ST HL AE-oAGE 44.0iF 7B.1 DISCUSSION An analysis was conducted to develop a response to Regulatory Guide (RC) 1.97, Rev. 2. This analysis identified the appropriate variables and established appropriate design bases and qualification criteria for instrumentation employed by the control room operr. tor during and following an accident.
This design basis establishes the key and preferred backup variables to be monitored by the control room operating staff of the South Texas Project (STP)    X
                                                                                         ^
following the initiation of an s.ccident. The design basis recognizes the variables essential to the ontrol room staff up to the time other ,(mergency      A reg genst7 0 . . c ir; [acilities are manned as well as the information essential to X the control room staff in subrequently controlling the plant and proceeding to safe shutdown conditions. Also included, to aid the system designer,are cri-      X teria for determining the requirements for the instruments used to mEnitor these variables.
The selection of variables was integrated with the Westinghouse Owners Group (WOG) Emergency Response Guidelines (ERGS) in accordance with the guidance on integration of energency response capability elements outlined in NUREG-0737 Supplement 1 (See Appendix 7A, Item S.3).
This was accomplished by performing a task analysis based upon the WOG ERCS to identify those variables necessary for implementation of the guidelines. The      40 Optimal Recovery Guidelines (ORGs) were reviewed to determine those Type A        Q32.
variables necessary to (a) perform diagnosis, (b) take preplanned manually        18 controlled actions and (c) take actions necessary to reach and maintain a con-trolled condition. The Critical Safety Function (CSF) Status Trees were reviewed to determine those Type B variables necessary for the operator to determine if a Functional Restoration Guideline (FRG) should be implemented.
Furthermore, the FRGs were reviewed to determine those Type B variables neces-sary to assess the process of accomplishing or maintaining CSFs, i.e., sub-criticality, reactor core cooling, heat sink maintenance, RCS integrity, con-tainment environment and RCS inventory. The ERGS were also reviewed to deter-mine those Type D variables necessary for (a) monitoring those plant safety systems employed for mitigating the consequences o' an accident and subsequent plant recovery and (b) other systems normally employed for attaining a cold shutdown condition. Finally, the ERGS were reviewed to determine those Type E variables necessary to (a) determine the accessability of areas at the plant following an accident and (b) continually assess the release of radioactive materials due to the accident.
Utilization of this task analysis process ensures that the plant information utilized by the plant operators following an accident to implement the STP Emergency Operating Procedures (EOPs) is obtained from specially designed and qualified instrumentation as defined in this design basis.
The WOG ERGS, the results of the Control Room Design Review (see Appendix 7A, Item I.D.1), and the interpretation of RG 1.97 Revision 2, as described in this Appendix, will be used to develop STP E0Ps that are human factored, function oriented, and integrated with the plant design.
7B.1-1                     Amendment 43          l 1
J

ATTACHM(m0NT      I STP FSAR                 ST HL-AE.                       ,
PAGE 45 OF 8l Apptndix 7B The de*_ ailed methodology for the handling of displays was addressed g the design of the Qualified Display Processing System (QDPS) and in conjuption            [      =
with the Control Room Design Review programs to address NUREG-0696 and NUREG-0700 (See Appendix 7A, Item S.5). Section 7B.3 describes interface criteria which must be satisfied for the display methodology to meet the in-tent of RG 1.47 Revision 2 and this design basis.
7B.1.1     Planned Versus Unplanned Operator Actiors                                 40 Q32.
The plant safety analyses and evaluations define the design basis accident           16 event scenarios for which preplanned operator actions are required. Accident monitoring instrumentation is necessary to permit the operator to take required actions to address these analyzed situations. However, instrumen-tation is also necessary for unplanned situations (i.e., to ensure that, should plant conditions evolve differently than predicted bf the safety anal-yses, the operator has sufficient information to monitor ti.e course of the event). Additional instrumentation is also needed to indicate to the operator whether the integrity of the fuel clad, the Reactor Coo 1. ant System (RCS) prec-sure boundary, or the reactor containment has degraded beyond the prescribed limits defined as a result of the plant safety analyses and other evaluations.
Such additionni requirements are considered by this design basis.
7B.I.2     Variables Types Five classifications of variables have been identified. Operator manual ac-tions identified in the operating procedures, associated with design basis accident events, are preplanned. Those variables that provide information needed by the operator to perform these manual actions are designated Type A.
The basis for selecting Type A variables is given in Section 7B.2.2.1.
Those variables needed to assess that the plant critical safety fuictions are being accomplished or maintained, as identified in the plant safety analysis        40 and other evaluations, are designated Type B.
Variables used to monitor for the significant breach or the potential signif-icant breach of fuel clad, the RCS pressure boundary, or the reactor contain-ment, are designated Type C. Type C variables used to monitor the potential            '
breach of containment have an arbitrarily-determined, extended range. The extended range is chosen to minimize the probability of instrument saturation even if conditions exceed those predicted by the safety analysis. The response characteristics of Type C information display channels allow the con-trol room operator to detect cenditions indicative of significant failure of any of the three fission product barriers or the potential for significant failure of these barriers. Although variables selected to fulfill Type C functions may rapidly approach the values that indicate an actual significant failure, it is the final steady-state value reached that is important.
Therefore, a high degree of accuracy and a rapid response time are not neces-sary for Type C information display channels.
Those varinbles needed to assess the operation of individual safety systems                     1 and systems normally used to attain cold shutdown are designated Type D.
7B.1-2                    Amendment 40 i

r
                                                                 --ATTACHMENI i
                            -                   STP FSAR          ST-HL AE- N30 Appandix 7B          PAGE tilo 0F fl l
The variables that are required for use in determining the magnitude of                       ;
f    release and continually assessing any releases of radioactive materials are designated Type E.
      -The five classifications are not mutually exclusive in that a given variable (or instrument) may be included in one or more types. The cross-referencing              y ef[ariableto[ypeisgiven.inTable 7 3. 9- 1. '*- '7,,5~- 1
      -Tab.le'18.   -l ' identifies the instruments utilized at STP which address the 7".j^
                                                                                                /
recommendations of both NUREG-0737 and RG 1.97 Revision 2.         The instruments identified meet the intent of the guidance provided in NUREG-0737.
78.1.3     Design and Qualification Criteria Three categories of design and qual!fication criteria have been identified.
The differentiation is made in order that an importance of information hier-archy can be recognized in specifying post-accident monitoring instrumen-tation. Category 1 instrumentation has the highest pedigree and should be              40 utilized for primary information which the operator should use for preplanned manual actions and determining the state of the plant. Category 2 and 3 in-                   ,
struments are of lesser importance in determining ,of the plant and do not                    l require the same level of operational assurance. \,4,4                                       i M
The primary di erences between category requirements are in qualification, application of single failure criterion, power supply, and display require-              /
ments. Category I requires seismic and environmental qualification, the application of a single failure criterion, utilization of emergency standby
{    power, and an immediately accessible display. Category 2 requires quali-fication commensurate with the required function but does not require the single failure criterion, emergency standby power, or an immediately accessible display. Category 2 requires, in effect, a rigorous performance verification for a single instrument channel. Category 3 does not require qualification, single failure criterion, emergency standby power, or an
       -immediately accessible display.
(
7B.1-3                    Amendment 40

L ATTACHMENT l ST HL-AE- 14i%                       N
             ),                       7
                                          ,PAGE e OF BT                 1 gg.,
f06'          (      '/
g6yg (cg 0               STP FSAR                       % bit WGV#d p/       g                          Appendix 7B                        p 7 f./g -/ fo 7 O l'Y d                  o#
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                               ),O'                      g.l TABLE 7B.10-1
                                                                                            ~
Y Y        O     g W                                                 hotpen cese h                              NUREG-0737Cd//dAWff                                             y Applicable Section of NUREG-0737 o                                  Varia'A e'-
ay SJety Valve.
: h. II.D.3                                          Pressurizer PORVA Status                      )(
ment O7    II.F.1 Attach 4                              Containment Pressure (Extended Range) h II.F.1            Attach
                                      ,g Containment Water LevellWdt N*T.
ava Nau w Racp')
Y h II.F.1 ~ Attach 6                                 Containment H    2 Concentration II.F.2                                       Core Exit Temperature klater Reactor Vessel3 Level                     Y RCS Subcooling                           40 h I.D.2                                             Emergency Response Facilities y
Data Acquisition and Display h      I.E.1.2 ment Auxiliary Feedwater Flow II.F.1 Attach 3                               Containment h Radiation                       A
                                    ^                     9(iigh Ran W nent II.F.1 Attach 2                               Unit Vent Sample
                                    ,,g                    c.naense. Vacuum Tap b @c.                  lA II.F.1 Attachpl                               Unit Vent A cticit;                          X ex~
Condense 44. Vacuum Pump Ef fim. .          X Me4* Steamline Radiation                    y ECCS and Other Systems Valve O// II.K.1.5                                          Status 1-9 7B. M                            Amendment 40

                                               ^                     ATTA.CHMENT I ST-HL-AE- IWD PAGE 8 OF 85                                                     l 3.fP FSAR Appendix 7B 7B.2 DEFINITION OF VARIABLE TYPES
[
7B.2.1 Definitions                                                                                                               I 78.2.1.1 Design Basis Accident Events. Pesign basis accident events are those events, any one of which.may occur du ing che lifetime of a particular plant, and those events not expected to occur A , postulated because their consequences would include the potential for release of significant amounts of radioactive gaseous, liquid, or particulate matet'ai to the environment.
j   Excluded are those events (defined as " normal" and " anticipated operational l   occurrences" in 10CFR50) expected to occur more frequently than once during the lifetime of a particular plant. The limiting accidents that were used to                                                     l determine instrument functions are: 1) LOCA, 2) Steamline Break, 3) Feedwater Line Break, and 4) Steam Generator Tube Rupture.
7B.2.1.2   Safe Shutdown (Hot Standby). The state of the plant in which
 ,   the reactor is suberitical such that K       is less than or equal to 0.99 and io'  the RCS temperature is greater than or*kual to 350*F.
7B.2.1.3 Cold Shutdown. The state of the plant in which the reactor is suberitical such that K      is less than or equal to 0.99, the RCS temperature islessthan200*F,and*beRCSpressureislessthanorequalto10CFR50 Appendix G limits.
78.2.1.4 Controlled Condition. The condition that is achieved when the                                                40 plant has been stabilized using the ORG D the recovery procedures are being                                                   /
( 1mplemented and the critical safety functions are being accomplished or main-taintd by the control room operator.
7B.2.1.5 Critical Safety Functions. Those safety functions that are es-sential to prevent a direct and immediate threat to the health and safety of                                                     <
the public. These are the accomplishing or maintaining of:
: 1. suberiticality
: 2. reactor core cooling
: 3. heat sink maintenance o
: 4. RCS integrity
: 5. containment environment
: 6. RCS inventory 7B.2.1.6 Inunediately Accessible Information. Information that is visu-ally available to the control room operator, or is accessible through the exe-cution of the EOPs.
7B.2.1.7 Primary Information. Information that is essential for the direct accomplishment of the preplanned mantal actions specified in the ERCS; it does not include those variables that are associated with contingency
( actions.
l 7B.2-1                         Amendreent 40                                                   l

ATTACHMENT I ST-HL AE-14So AGE IM OF 8\
STP FSAR Appendix 7B 7B.2.1.8 Key Variables. Those variables which provide the most direct measure of the information required.
7B.2.1.9 Back Information. Back!informationisthatinformation,madeup                                                             [
cf additional variables beyond those classified as key, that provides cupplemental and/or confirmatory information to the operator. Backup vari-cbles do not provide an indication which is as reliable or complete as that provided by. primary' variables, and they should not be relied upon as the sole cource of information. Those backup variables which should be first consulted by the operator are designated as preferred backup variables.
7B.2.2         Variable Functions The accident monitoring variables and information display channels are those that are required to enable the control room operating staff to perform the functions defined by Types A, B, C, D, and E below.
7B.2.2.1 Type A. Type A variables are those variables that provide the primary information required to permit the control room operating staff to:
o        Perform the diagnosis specified in WOG ERGS e        Take the specified preplanned manually controlled actions for which                                  40 r.o automatic control is provided, that are required for safety systems to accomplish their safety function in order to recover from the Design Basis Accident (DBA)[ vent,and e        Reach and maintain a safe shutdown condition.
     'The verification of the actuation of safety systems have been excluded from the definition of Type A. The variables which provide this verification are included in the definition of Type D.
Variables in Type A are restricted to preplanned actions for EBA events.
7B.2.2.2 Type B. Type B variables are those variables that provide to the control room operating staff information to assess the process of accomp-lishing or maintaining critical safety functions, i.e., suberiticality, reac-tor core cooling, heat sink maintenance, RCS integrity, containment environ-
  #g  menthRCSinventory. The WOG contingency guidelines which go beyond the                                                               [
design basis were reviewed for additional variables which may be utilized as variable types B, C, D, and E.
7B.2.2.3 Type C.       Type C variables are those variables that provide the control room operating staff information (1) to mor.itor the extent to which variables which indicate the potential for causing a significant breach of a fission product barrier have exceeded the design basis values and (2) that the fuel clad, the reactor coolant system pressure boundary (RCPB) or the reactor containment may have been subject to significant breach. Excluded are those associated with monitoring of radiological release from the plant which are included in Type E.                                                                                                                 ,
7B.2-2                                                  Amendment 40

r     .
ATTACHMENT I ST-HL AE- WID STP FSAR  PAGE 40 OF 3)
Appendix 7B Type.C variables used to monitor the potential for breach of a fission product
(     barrier have an arbitrarily-determined, extended range. The extended range is chosen to minimize the probability of instrument saturation even if conditions exceed those predicted by the safety analyses.
7B.2.2.4 Type D.         Type D. variables are those variables that provide to the control room operating staff sufficient information to monitor the performance of:
: 1. Plant safety systems employed for mitigating the consequences of an acci-dent and subsequent plant recovery to attain.a safe shutdown condition (These include verification of the automatic actuation of safety systems).
40 A
: 2. Systems normally employed for attaining a cold shutdown condition.
7B.2.2.5 Type E.s Type E variables are those variables that provide to the control room operating staff information to:
: 1. Monitorthehabitdbilityof/controlroom,                                                     h
: 2. Monitor plant aret.s where access may be required to service equipment necessary to monitor the progress of or mitigate the consequences of an accident.
: 3. Estimate the magnitude of release of radioactive materials through identi-fied pathways, and continually assess such releases, and
(-   4. Monitor radiation levels and radioactivity in the environment surrounding the plant (via portable monitors).
l l
1 7B.2-3               Amend:sent 40

F ATTACHMENT I STP FSAR Appsndix 7B        ST PAGEHLt;IAE 0F Nfo@
7B.3 CRITERIA 7B.3.1     General Requirements The following design and qualification criteria are applied to instrumentation for Type A,"B, C, D and E variables. These are summarized in Tables 7B.3-1 and 7B.3-2.                                                           ,
7B . 3". 2 Equipment Design and Qualification Criteria.
The qualification _ requirements of the Type A, B, C, D, and E accident moni-
    .toring instrumentation are subdivided into three categories (1, 2, 3).
Descriptions of the three categories are given below.- Table 7B.3-2 briefly summarizes the design and qualification requirements of the three designated categories.
7B.3.2.1   Design and Qualification Criteria - Category 1.
7B.3.2.1.1 Selection Criteria - Category 1: The selection criteria for Category 1 variables have been subdivided according to the variable type. For Type A, those. key variables used for diagnosis or providing infornation for necessary operator action have been. designated Category 1. For fype B, those         X key variables which are used for monitoring the process of accomplishing or maintaining critical safety functions have been designated Category 1. For Type C, those key variables which are used for monitoring the potential for         40 breach of a fission product barrier have been designated-Category 1.
as amassed 7B.3.2.1.2 Qualification Criteria -       tegory 1: The instrumentation is environmentally and seismically qualifiedy n .;;;rd_r.;; sin FC.'? Sections          N 3.11 and 3.10, respectively.      Instrumentation continues to read within the required accuracy following but not necessarily during a seismic event. At least one instrumentation channetfis qualified from sensor to display. For           %
the balance of instrumentation channels, qualification applies up to and including the channel isolation device.       (Refer to Section 7B.3.3 in regard to extended range instrumentation qualification).
7B.3.2.1.3   Design Criteria - Category 1:
: 1. No single failure within either the accident monitoring instrumentation, its auxiliary supporting features, or its power sources, concurrent with the failures that are a condition of or result from a specific accident, prevents the operator from being presented the required information.
Where failure of one accident monitoring channel results in information ambiguity (e.g., the redundant displays disagree), additional information is provided to allow the~ operator to analyze the actual conditions in the plant. This is accomplished by providing additional independent channels of information of the same variable (addition of an identical channel), or by providing independent channels which monitor different variables which bear known relationships to the multiple channels (addition of a diverse channel (s)). Redundant or diverse channels are electrically irdependent and physically separated from each other, to the extent practicable with train separation, and from equipment classified as mensafety-related in accordance with RG 1.75.
W 7B.3-1                       Amendment 40

ATTACHMENT l ST-HL AE- lL 70 STP FSAR                  PAGE 6pO        M Appsndix 7B s
For situations such as isolation valves in series, the intent is generally                           ,
to verify the isolation function.      In such a situation a single indication on each valve is sufficient to satisfy the single failure criterion if                         _
those indications are from different trains (i.e., unambiguous indication of isolation).     .
If ambiguity does not result from failure of the channel, then a third redundant or di. verse channel is not required.
     ' 2. The instrumantation is energized from station emergency standby power sources, battery backed where momentary interruption is not tolerable, as rr--i'M i- RG 1. 32.
            &<es %
The out-of-service interval is based on normal Technical Specification 3.
requirements on out-of-service for the system it serves where applicable or where specified by other requirements.
: 4. Servicing, testing, and calibration programs are specified to maintain the capability of the monitoring instrumentation. For those instruments where        '
the required interval between testing is less than the normal time inter-val between generating station shutdown, a capability for testing during         l        N power operation is provided.              $                                      f40
: 5. Whenever means for removing channels from service are included in the design, the design facilitates administrative control of the access N
y such removal means.
: 6. The design facilitates administrative control of the access to setpoint adjustments, module calibration adjustments, and test points.
i
: 7. The monitoring instrumentation design utilizes human-factored displays to minimize indications potentially confusing to the operator.                               -           i
: 8. The instrumentation is designed to facilitate the recognition, location, a            replacement, repair, or adjustment of malfunctioning components or l           modules.
!      9. To the extent practicable, monitoring instrumentation inputs are from i            sensors that directly measure the desired variables. An indirect measure-ment is made only when it can be shown by analysis to provide unambiguous information.
: 10. Periodic checking, testing, calibration, and calibration verificatico are in accordance with the applicable portions of RG 1.116.
J
: 11. The range selected for the instrumentation encompasses the expected oper-ating range of the variable being menitored to the extent that saturation                            ;
does not negate the required action of the instrument in accordance with                             !
the applicable portions of RG 1.105.
73.3.2.1.4 Information Processing and Display Interface                                              i
[       Criteria - Category 1: The interface criteria specified here                           I Provide ( requirements implemented in the establishment of the design basis for                 N. 8 processing and displaying of the information.
7B.3-2                     Amendment 40

ATTACHME                                                    !
                                                                                                                                /
ST-HL-AE- I STP FSAR PAGE G3 OF $
Appendix 7B
: 1. The operator has immediate access to the information from redundant or di-(                                              verse channels in the units familiar to the operator (e.g.,'for a temper-aturereadinggegreesnotvolts). Were two or more instruments are needed to cover a particular range, overlapping of instrument spans are
                                                                                                                                                                      )(
provided.
                                                        ^
A              y               2.   .. hi:t:rie:1 ::;e d ;f ; :.:nir Of ;;; i..e6          aaien ;t;.;; 1 fer --9 jr : a ..sieL1. 1. -ointained. A recorded pre-event history for these                                            .
channels is required for a minimum of one hour and continuous recording of these channels is required following an accident until such time as con-tinuous recording of such information is no longer deemed necessary. This recording is available when required, but need not be immediately acces-sible. One hour was selected based on a representative slow transient p                         -
wnich is oun -by this time requirement. A one-half inch equivalent break area Loss-o -Coolant Accident (LOCA) was selected since trip occurs at ap-4 proximately fifty minutes after break initiation. Were direct and imme-diate trend or transient information is essential for operator information or action, the recording,is immediately accessible.
1 7B.3.2.2 Design and Qualification Criteria - Category 2.
7B.3.2.2.1   Selection Criteria - Category 2: The selection criteria for Category 2 variables are subdivided according to the variable type. For Types A, B, and C, those variables which provide preferred backup information are
-                                                  designated Category 2.      For Type D, those k   variables that are used for non-
,                                                  itoring the performance of safety system         e designated Category 2. For                                    40 )
Type E, those key variables to be monitored for use in determining the mag-
 ' '{-                                             nitude of the release of radioactive materials and for continuously assessing such release         designated Category 2.                                                                         Ml 7B.3.2.2.2 Qualification Criteria - Category 2: Category 2 instrumen-tation is qualified from the sensor up to and including the channel isolation device for at least the environment *(seismic and/or environmental) in which it must operate to serve its intended. function. Instrumentation associated with those safety-related systems that are required to operate following a Safe o
Shutdown Earthquake (SSE) to mitigate a consequential plant incident are seis ,
mically qualified in accordance with IEEEf344-1975. Category 2 instrumenta-
[
tion is environmentally qualified in accordance with IEEE 323-1974.                                               X h
:                                                       7B.3.2.2.3   Design Criteria - Category 2:
4
: 1. Category 2 instrumentation associated with those safety-related systems
,                                                       that are required to operate following an SSE to mitigate a consequential plant incident are energized from -c-!--icelly ;;1144ed power source,
,                                                      not necessarily the en'ergency standby power, which is battery-backed where momentary interruption is not tolerable. Geheew6ee-sh: in:: n .:;;i;; 1; crrr;;ie ' frc: c 'hi;;hly reltati; en :10: ;=:: ::::::, nrt 20 :::::117 :h;
                                                         -- :-- y -*- '57 ;rrr, --hich i: Sett:ry 5::h:f d.;;; ::::;;:ry int:; ;g tic i: :: ::1;;;ti;.                                            yak
: 2. The out-of-service interval is based on normal Technical Specification j [                                                    requirements on out-of-service for the system it serves where applicable
        \                                              or where specified by other requirements.
i i
2
;                                                                                         73.3-3                              Amendment 40

ATTACHMENT l
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1 1

ATTACHMEN I STP FSAR                                      ST HL-AE Di 0 Appendix 7B                                      PAGE % OF El 7B.3.2.3.3 Design Criteria - Category 3:
: 1.          Servicing, testing, and calibration programs are specified to maintain the capability of the monitoring instrumentation. For those instruments where the required interval between testing is less than the normal time inter-val between generating station shutdowns, a capability for testing during power operation is provided.                                                             .
: 2. "Whenever means for removing channels from service are included in the
 ;                                                      design, the design facilitates administrative control of the access to such removal means.
: 3.           The design facilitates administrative control of the access to setpoint adjustments, module calibration adjustments, and test points.
: 4.           The monitoring instrumentation utilizes human-factored displays to mini-mize indications potentially confusing to the operator.
: 5.           The instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.
: 6.           To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables. 'An indirect measure-4 ment is made only when it can be shown by analysis to provide unnabiguous information.
7B.3.2.3.4 Information Processing Display, Interface Criteria -
Category 3: The interface criteria sTecified here provide                               40 requirements considered in the establishment of the design basis for proces-sing and displaying of the information.
                                      - The instrumentation signal is, as a minimum, processed for display on demand.
Recording requirements are variable specific and are determined on a case-by-case basis.
7B.3.3 Extended Range Instrumentation Qualification Criteria The qualification environment for extended rang: information display channel I
components are based on the design basis accident events, except the assumed maximum of the value of the monitored variable is the value equal to the spec-ified maximum range for the variable. The monitored variable is assumed to approach this eak by extrapolating the most severe initial ramp associated with the DBA ents. The decay for this' variable is considered proportional to the decay or this variable associated with the DBA vents. No additional qualificationmarginneedstobeaddedtotheextended[rangevariable. The                                                   [(
                                                                                                                                                             )
environmentc1 envelopes, except that pertsining to the variable measured by the information display channel, are those associated witi the DBA The environmental qualification requirement for extended range equ paent does ents. K not account-for steady-state elevated levels that may occur'in other environ-
.                                        mental parameters associated with the extended range variable. For example, a sensor measuring containment pressure must be qualified for the measured 4    - (-                                process variable range (i.e., 3 times design pressure for concrete 1
7B.3-5                                                Amendment 40
      - _ . _ _ _ ~ . , _ _ _ _ _ _ _ . _ _ _ . _ _                                   _ _ _ . . _ _ _ . _ . _ , _ - . _ _ . - .                        ,    _ . .

                                                                                                                                          ~
I ATTACHMENT i STP FSAR                                    ST HL-AE WJD PAGE 4L, OF 8l Appendix 7B containments), but the corresponding ambient temperature is not mechanis-tically linked to that pressure. Rather, the ambient temperature value is the bounding value for design basis accident events analyzed in Chapter 15.;f ;;. o y . The extended range requirement is to ensure that the equipment will                                                           40 continue to provide information if conditions degrade beyond those postulated in the safety analysis. Since extended variable ranges are nonsechanistically determined, extension of associated parameter levels is not justifiable-and is therefora not required.
i 7B.3-6                                        Amendment 40

N Table 7B.3-1 Summary of Selection Criteria CATEGORY 2                       CATEGORY 3 TYPE     CATECORY 1 Variables which provide          None              ,
A      KEY variables that are used                                                             '
for diagnosis or providing    PREFERRED BACKUP information.
information for necessary operator action.                                                               ~
Variables which provide           Variables which provido B      KEY variables that are used                                     BACKUP information.
for monitoring the process of PREFERRED BACKUP information.
accomplishing or maintaining                                                                                 ^
critical safety functions.
Variables which provide           Variables which provide u   C       KEY variables that are used                                     BACKUP information.                40 m for monitoring the potential  PREFERRED BACKUP information.                                           Y F
Y            breach of.a' fission product                                                                          g
                "            barrier.
N KEY variables which are used     Variables which provide PREFERRED D        None for monitoring the performance   BACKUP information rM ' crr cred    N of plant systems used to attain for$o#"itoringtheperformancenf n                               /
a controlled plant condition or plant systems used to attain a controlled plant condition or a a safe shutdown condition.
safe shutdown condition.
KEY variables to be monitored    Variables to be monitored which E       None                                                           provide PREFERRED EACKUP informa-   MD for use in determining the magnitude of the release of       tion for use in determining the         y radioactive materials and       magnitude of the release of radio-       g i                                           for continuously assessing       active materials and for continu-  _smg
                $                                           such releases,                   ously assessing such releases.      g
{E                                                                                                               9   .,_
8 1

ATTACHMENT
                                                                                                               . A             0 SYP FSAR                                                                 gg Table 75.3-2 Summary of Design, Qualification, and Interface Requirements 1
(
Category 1_
Y hCategory 2                                                   a Category 3_
Qualification             ,
Environmental                         Yes                              As appropriate U) No                                 ,
1 e
Seismic                               Yes                              As appropriate Q) No Design Single Failure                        Yes                               No                                           No Power Supply                           Emergency                        Reliable                                     As Required Standby                                                                                         40        l l
Channel out of Service                Technical                         Technical                                    No Specifications                    Specifications Testability                           Yes                                Yes                                         As Required                 l Interface Minimum                                Immediately                       Des.and                                     Demand Indication                             Accessible Recording                              Yes                               As Required                                 As Required Qualdi A 55 cram (                                                                              .
f-
                                                                          = i " " "' " T " '
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                      .gu a crua h i rttl & Tf*" %                                                                                   JYT*
T
!                      rd E m d atte m -                                                                         Amendment 40 75.3-8

STP FSAR     '-ATTACHMENT I Appandix 7B             AE FifD ST PAGEHL69 OF    R\
7B.4 TYPE A VARIABLES 7B.4.1 Introduction Type Ag[ariables are defined in Section 7B.2.2.1. They are the variables           /(
which provide primary information required to permit the control room operating staff to:                                                .
: 1. JPerform'the diagnosis specified in the WOG ERGS
: 2. Takespecifiedpreplannedmanuallycontrolledactionsfforwhichnoauto-                /(
matic control is provided, that are required for safety systems to accom-      40 plish their safety function to recover from the DBAp K'v ent (Verification of  f(
actuation of safety systems is excluded from Type A and is included as Type D);
: 3. Reach and maintain a safe shutdown condition O            Key Type A variables have been designated Category 1. These are the variables which provide the most direct measure of the information required.
No Type Aj V'ariables have been designated Category 2 or 3.                        )(
The Type A variables are listed in Table 7B.4'1.
.                                                                                                         i 1
l i
7B.4-1                        Amendment 40

STP FSAR                  ATTACHMEN I Appindix 7B                 ST HL-AE. m b PAGE (,0 OF M TABLE 7B.4 1 hotore cas g                   y SW1 ht Thf A V)(f//jff)
C ieseri    /
: 1. RCS Pressure (Wide Range)                                                        Al
: 2. Hot Leg Reactor Coolant Temperature (Wide Range T                  )             Al
                                                                                               /
: 3. Cold Leg Reactor Coolant Temperatur5 (Wide Range Tcold}                          ^
W4Ter
: 4. Wide Range Steam Generator      g Level                                          Al       X (130ft f
: 5. Narrow Range Steam Generator3 Level                                              Al        Y U)e tt f
: 6. Pressurizerg level                                                               Al       5
: 7. Pri : 7 2 ::::: Containment Pressure                                             Al        X
: 8. Steamline Pressure                                                               Al
: 9. Refueling Water Sterage Tank (RWST)4L evel                                       Al       )(
: 10. Containment Water Level (Wide Range)                                             Al 40
: 11. Containment Water Level (Narrow Range)                                           A1 (AFp(ST's kJa4er
: 12. Auxiliary Feedwater Storage Tank Level 3
Al     )(
: 13. Auxiliary Feedwater Flow                                                         Al l 14. High Range Containment Radiation Level                                           Al
: 15. RCS Pr       - re (Extended Range)                                                Al LNd                                      X
: 16. Steam b ...cator Blowdown Radiation M: nit:r-                                    Al Lv er
: 17. Steamline Rediation          ."enn.e.\                                           Al       /
: 18. Core Exit Temperature                                                            Al
: 19. RCS Subcooling                                                                    Al n
7B.4-2                        Amendment 40

                                                                            =
STP FSAR      ATTACHMENT I ST-HL-AE- NfD Appzndix 7B      PAGE lA OF $
7B.5 TYPE B VARIABLES 7B.5.1   Introduction Type B variables are defined in Section 7B.2.2.2. They are the variables that provide to,the control room operating staff information to assess the process of accomplishing or maintaining critical safety functions, i.e.,
                                                                  ~
1..Suberiticality
: 2. Reactor Core Cooling
: 3. Heat Sink Maintenance Reac.or d
Coelant S 3 mm                                                          40 4.gCS) Integrity                                                                  Y
: 5. Containment Environment Reo& Cooknt $3 stem 6 4(RCS) Inventory                                                  (
Variableswhichprovidethemostdirectindication(i.e.,[f/ variables)to                X assess each of the 6 critical safety functions have been designated Category
: 1. Preferred backup variables have been designated Category 2. These are listed in Table 7B.5 gl. All other backup variables have been designated          y Category 3.           g l
7B.5-1                       Amendment 40

STP FSAR                  ATTACHMENT [
AppIndix 7B                  ST-HL-AE- 1430 PAGE WOF 8\
Table 7B.5fl                                                    X Summary of Type B Variables Categ ory       K Subcriticality         . Key:                a. Neutron Flux (Extended Range) B1
: b. Neutron Flux Startup Rate              B1
                                                                                           ~
Preferred            a. Wide Range T                           B2        N Backup:              b. Wide Range gold Reactor Core Cooling    Key:                 a. Core Exit Temperature                  B1
: b. Reactor Vessel Water Level             B1
: c. RCS Subcooling                         B1
: d. AFS     evel                           B1     Y
  *,                                              e. RWS Level w 4tr B1      }
Preferred            a. Wide Range T                           B2      /
Backup:              b. Wide Range                             B2      X
: c. RCS Pressur TN)                        B2      Y E     et Heat Sink Maintenance   Key:                 a. Narrow Ra           Level              B1    /
: b. k'ide Rang     %-Level                 B1    y
: c. Auxiliary Feedwater Flow               B1 g     T        d   MfrT- Level                            B1     )r M            e. Steamline Pressure
                                                    .                                        B1
: f. Core Exit Temperature                  B1
: g. Wide Range T                           B1  %
                                                ~h. Wide Range od Preferred            a. Main Steamline Isolation               B2 Backup:                  Valve Status
: b. Main Steamline L,vlaim.         #      B2   X Bypass Valve Status Reactor Coolant System  Key:                 a. RCSPressure(W[                         B1    Y (RO} Integrity                                    b. RCS Pressure (Extended Range) B1              y Preferred            a. Containment Pressure                   B2 Backup:              b. High Range Containment Radiation Level          v             B2
: c. NarrowRangeSGhve4u         l           B2      #
GG d. 9fe-Blowdown Radiation Level                   B2      Y Steamline Radiation Level              B2
: f. Pressurizer PORV Status                B2
: g. Pressurizer Safety Valve Status                                 B2 7B.5-2                                     Amendment 40

ATTACHMENT I ST-HL-AE LWD STP FSAR            PAGEla OF 8l Appendix 7B l
Table 7B.5         (Continued)                                 y Summary of Type B Variables j                                                            Coiegoc1   )
?. ;; ::   s/            Key:             a. Containment Pressure-             B1 1
Containment Environment                   b. High Range Containment.
              ,                                Radiation Level           r    e. B1
: c. Containment Water Level ( W       B1    Y
: d. Containment Hydrogen              B1 Concentration 0
Preferred        None Backup:
                                                         %W                             #
Reactor Coolant          Key:             a. Pressurizer, Level                B1 Sysi:em Inventory                         b. Reactor Vessel Water Level        B1     Y A                                                                   aleRaqL-Preferred             Containment Water Level (         B2      X QO)                               a.
Backup:          b. Containment Water Level (NA-)     B2      y
: c. Wide Range Steam Generator        B2 A                                Narrow Ea ng g, tueW 7B.5-3                            Amendment 40

ATTACHMEb    i ST-HL-AE F 7B.6 TYPE C VARIABLES 7B.6.1     Introduction Type C variables are defined in Section 7B.2.2.3.       Basically, they are the variables that provide to the control room operating staff information to mon-itor the potential for breach or actual significant breach of:
: 1. Fuel Clad; (R6)                                    -
y
: 2. Rpactor oolant System Boundary; 3        or
: 3.  "can s. Containment Boundary.
(Variables associated with monitoring of radiological release from the plant are included in Type $                                                              N Those Type C key variables which provide the most direct measure of the h/ATENTIALforbreachofoneofthe3.fissionproductboundarieshavebeendes-                   /
ignated Category 1. Backup information indicating potential for breach is designated Category 2. Variables which indicate actual breach have been des-ignated as preferred backup information and have been designated          Category   [
: 2. All other backup variables have been designated Category 3.
Table 7B.6-1 summarizes the selection of Type C variables.
7B.6-1                     Amendment 40

gh T Mi h*I k         p ld                                    HL       0 p*
STP FSAR     PAGE(16 0 RI                  '/ [              g yy j) p VW App;ndix 7u hU hA\p                     ,
b                                            TABLE 7B.6                                          I          E Summary of Type C Variables
: c. cw" #                                Sr POTENTIAL FOR BREACH          C. hoe t ACTUAL BREACH g                     O*D 8# ' '         y IN-CORE   ,
Key:        e Exg Temperature           Backup: RCSSampling(C3f-                ?           )
FUEL CLAD:
(Cl i, Backup:
                           ";;ferr;d Reactor
                                                                                                                    /
IVessel Water Level (C2)
RCS BOUNDARY   Key: RCS Pressure (Cl)--+              preferredBackup:       RCS Pressure                   b (Extended Range)                4       W              (Wide Range)                      )r (C2)                           )
RCS Pressure (Cl) -->                                 Containment M                    p (Wide Range)                                           Pressure (C2)1
                                                                                                                      }
ContainmentWatep                   >
tad. R* *H       Lev          (C2)
Containment Waterp-                 J M0 N** D3t.      Levep (C2)- J                      >
Steamline Rndi- p't                  ;
ation Level (C2)I 40 SG (W e Blovaovn                                 ,
Radiation Level                      #
(C2)
High Range Containment Radi
                                                                               ,ation Level (C2)
CONTAINMENT    Key: Containment Ecessure }PraferredBackup:'UnitVentRadi-                                           )
(Extended Range) (Cl)            t      A              Ption Level (C2) b0UNDARY                                                          g gyp A us T' Fuel Handlin         .,
ContainmentJressure (Wido
                                    -3,      (Cl)---+                             Buildin     adiation Level (C2)
Codm**JHydrogen Concentration                                    Containment Iso-(Cl)-                    )                            lation Valve Status (C2)
Containment Pres- 3 sure (Extended                       '
Range) (C2)--- -- ~~
7B.6-2                           Amendment 43

STP FSAR           ATTACHMENT l ST-HL AE Ngo Appzndix 7B         PAGE bb OFKi TABLE 7B.6-Q(Continued)
Summary of Type C Variables en W      Cyfrppi POTENTIAL FOR BREACH 44,      ACTUAL BREACH                     -
CONTAINMENT                                 Backup: Site Environmental          40 BOUNDARY (Cont'd)                                    Radiatfo g(Portable ked r Monitoring}(C3)P Adjacent Building   d Area Radiation      l Level (C3)-
7B.6-3                           Amendment 43 e

ATTACHMEN4 ST.HL-AE- N3     i STP FSAR         PAGE b10F 31 7B.7 TYPE D VARIABLES 7B.7.1    Introduction Type D variables are defined in Section 7B.2.2.4. Basically, they are those variables that provide sufficient information to the control room operating staff to monitor the performance of:                                 .
: 1. JPlant safety systems employed for mitigating the consequences of an acci-dent and subsequent plant recovery to attain a safe shutdown condition, including verification of the automatic actuation of safety systems; and
: 2. Other systems normally employed for attaining a cold shutdown condition.
bcaS t.
Typed /$/variablesaredesignatedCategory2. Preferred backup information                   )(
is designated Type D Category 3.
The following systems have been identified as requiring Type D information to be monitored:
: 1. Pressuriner Leve1 and Pressure Control (assess status of RCS following return to normal pressure and*1evel ebntrol under certain post-accident-conditions) 40
: 2. Chemical and Volume Control System (CVCS) (normally employed for attaining a safe shutdown under certain post-accident conditions)
: 3. Secondary Pressure and Level Control (employed for restoring / maintaining a secondary heat sink under post-accident conditions)
: 4. Emergency Core Cooling System (ECCS)
: 5. Auxiliary feedwater                                                              II T
: 6. Containment Systems
: 7. Component tooling water (CCW)                                                     )(
s
: 8. Essential Cooling Water (ECW) 63577m
: 9. Residual Heat Removal (RHR)3(normally employed for attaining a cold                hl shutdown condition)                                                     -
: 10. Heating, ventilation, and air conditioning (HVAC) if required for Engineered Safety Features operation
: 11. Electric power to vital safety systems
: 12. Verification of automatic actuation of safety systems                        t
    . Table 7B.7-1 lists the key variables identified for each system listed above and specifies the seismic and environmental qualification for each variable.
7B.7-1                         Amendment 40

ATTACHMENT (
ST.HL-AE fl480 STP FSAR                    PAGE 61 OF 8l Appendix 7B For purposes of specifying seismic qualification for Type D Category 2 vari-ables, it is assumed that a seismic event and a break in Category I piping will not occur concurrentiv. As a result, the limitinc event is an unisolated (Jsingle failure of a main steam ,'_y J Iation valve (MSIV)1) break in non-Category F main steam pipin f lustrumet. cation associated with the safety systems which    40 are required to mitigate and monitor this event should be seismically qual-ified instrumentation. Similarly, the environmental qualification for Type D Category 1. variables depends on whether the instrumentation is subject to a high-energy line break (HELB) when required to provide information.
7B.7-2                        Amendment 40

c                                                                                     ..
TABLE 7B 7-1 SoemmeH obType D           Variables                       ,
Y System Designation                     a r i ab le '- * -"- * -
* i -          Seismic         Environmental fategari   /t
: 1. PressurpzerLeveland         Pressurizer PORV 5tatus                      Ye s             HELB D2 PressurI. nee Control       Pressurizer PORV Block Valve Status          Yes              HELB            D2 Pressurizer Safety Valve Status              Yes              HELB            D2 Pressurizer Spray Valve Status               No               Ambient         D2 Pressurizer Heater Breaker Position          No               Ambient         D2 PressurizerAl evel a w c                     Yes              HELB            D2        Y Reactor Vessel Water Level                   Yes              HELB            D2 RCS Pressure ( g eo Je 43 g,                 Yes              HELB            D2          y Pressurizer Pressure                         Yes              HELB            D2 RCP Status                                   No               Ambient         D2
: 2. CVCS                        Charging Flow                                No               Ambient         D2 Letdown Flow                                 No               Ambient         D2
: y.                               g    VCT Level                                    No               Ambient         D2 y                                     Ro Seal Injection Flow                       No               Ambient         D2 40 )I h d,                                                                                 Yes (Isolation Valve Status                                                                                 5 valves only) Ambient          D2             $
Charging Pump Status                         Yes              Ambient         D2 BAT Pump Status                              Yes              Ambient         D2
: 3. Secondary Pressure and   SCrsf& PORV Status                              Yes              HELB*           D2       )(
Level Control               Main Steamline Isolation Valve Status        Yes              HELB*           D2 Main Steamline Bypass Valve Status
                                   $6 6/G-Safety Valve Status Yes Yes HELB*
HELB*
D2 D2      )/
[3 m
Steamline Pressure                           Yes              HELB*           D2           r>I MFW Control Valve Status                     Yes              HELB*           D2 g                                     MFW Control Bypass Valve Status              Yes              HELB*           D2            n z y                                     MFW Isolation Valve Status                   Yes              HELB*
D2          oo g                                     MFW Isolation            Bypass Valve Status Yes              HELB*           D2     )(
S
$     *These systems must be qualified to the worst case environment in which they must function (including HELBs inside and outside containment).
i

TABLE 7B.7-1   (Continued)
Susamert of Type D      ariables                       ,.,
System Designation                M Variable !-.M i.......ta '...
                                                       .                           Seismic    Environmental
: 3. Secondary Pressure          MFW Flow                                    No         Ambient            D2 and Level Control (Cont'd) Auxilipry Feedwater Flow                     Yes        HELB*              D2 6G S/t.)Svel (""' ...? (""'(Wdeba9# 8@7 )Yes              HELB               D2      X SG t/C-Blowdown Isolation Valve Status         Yes         * * ' ..; N Et,8#
D2     X SG S/C-Blowdown Sample Isolation Valve                                              I Status                                      Yes        Amh& ear $6L6'     D2 MIer                                                                     #
: 4. ECCS                        RWST evel                                   Yes        Ambient            D2 Teee4.HHSI Flow                             Yes        HELB**             D2     X 15es.e1.LHSI Flow        (QSyge JMrimoggo              HELB**             D2      )r Containment Water LeveT   4  (Z) onu (Z)-   No         HELB               D2     y Pump and Valve Status                       Yes        llELB**            D2 M                                      Accumulator Pressure                        Yes        HELB               D2 40 m
eg I. 5. Auxiliary Feedwater         Auxiliary Feedwater Flow.                   Yes        HELB*              D2 U
Pump and Valve Status              y, tats- Yes        HELBf              D2            $
Auxiliary Feedwater Storage TankgLevel      Yes        Ambient            D2    X
: 6. Containment Systems         Containment Spray Flow w ,g,q,a,gu, % % ,No            HELB**             D2 Containment Water Level % =} ono doa)       No         HELB               D2  X SpraySystegValveStatus                      No         HELB**             D2   j(    i
                                          , Fan Cooler Differential Pressure /                                       z Status                                     No         HELB               D2           yg3 f'g*pa          Containment Pressure                        No         HELB               D2 ph>g m
Containment Isolation Valve Status          Yes        HELB*              D2 Containment Ventilation Gemper Status       Yes        HELB*              D2  y        j$$
Nahl4                                                           Mm o$
a g                                                                                                                             T~
 ,,.  *These systems must be qualified to the worst case environment in which they must function (including HELBs inside and outside containment).
     **These systems may see radiation from components in the recirculation path.

TABLE 7B.7-1    (Continued)
So....y e/ Type D Mariables                                               y System Designation                    Variable ' m tr-;:ntrt'--             Seismic      Environmental (s try ,4 %
: 7. EfMCompohani bohnj            Pump Discharge Pressure                    Yes          Ambient             D2
(.uder                      Header Temperature                         Yes          Ambient             D2 Surge Tank Leve      W ater                Yes          Ambient             D2 Flow to ES     omponents                   Yes          llELB*              D2 Pump and Valve Status                      Yes          Ambient ///gt$      D2  %
: 8. Essential Cooling Water     Flow io GSF Comgewnts                      Yes          Ambient             D2  Y Syntr                       Pump and Valve Status                      Yes          MF4,A - O dent       D2 K
: 9. RHR System                  lleat Exchanger Discharge Temperature      No           HELB**               D2 Flow                                       No           llELB**              D2 Pump and Valve Status                      No           llELB**              D2 Yes          HELB                 D2 X RCS Pressure ( $ gg,j,g ,qg,,                                                       a
: 10. HVAC                         Environment       'SF "I~empey,'tuf t      Yes          HELB**               D2 W
: 11. Electric Pswer
                                      .sr c..      .. eser 51=ws Standby Power and Emergency Source yes           wa s *
* o2. Kl]px Status                                     Yes          Ambient              D2 Other Safety-Related Energy Sources        Yes          Ambient              D2 Reactor Trip Breaker Position              Yes          HELB                 D2 N
: 12. Verification of Auto-matic Actuation of          Turbine Covernor Valve Position            No           No                   D2 Safety Systems             Turbine Stop Valve Position                No           No                   D2    Kg Auxiliary Feedwater Pump Status                                                   ciH
  $'                                   (turbine)                                 Yes          HELBi                D2  Y *d y                                    Auxiliary Feedwater Pump Status (motor driven)                            Yes          HELB              g  D2 X  o m SI Pump and Valve Status                  Yes           a-h *    ,41 ELE    D2  X   g3 9-E                                 -
       *These systems must be qualified to the worst case environment in which they must function (including IIELBs inside and outside containment).
      **These systems may see radiation from components in the recirculation path.
l

TABLE 7B.7-1    (Continued)
So-1
* AType D d variables                                ,.
System Designation                   ariable  !...,a......; ;i. !          Seismic       Environmental   Ca%P3ai
: 12. Verification of Auto-       CCW Pump and Valve Status                  Yes     /bekMT[ELB             D2 matic Actuation of          ECW Pump and Valve Status                  Yes          i+Pt:fr AmEIPot   D2 Safety Systems (Cont'd)     Containment Spray Pump and Valve bratus Yes              "" t en: #Et5 d   D2          '
Neutron Flux (Extended Range)              Yes           HELB U           D2 Neutron Flux Startup Fate                  Yes           HELB F           D2 Containment Isolation Valve Status y, Joe. Yes           HELB*            D2 Containment Ventilation % ' Status         Yes           HELB*             D2 RCB Fan Cooler Differential Pressure /
Status                                     No            HELB             D2 SI Actuation Status                        Yes           Ambient           D2 Containment Isola on Actuation Status      Yes           Ambient           D2 Control Rod Position (Backup)              No            Ambient          D3          m 40 h&rcn%n i  S                                                                                                                       {
4 i
 )
N#4 -
j                                                                                                                         rn c)%>H l
g                                                                                                                     d i>
m a                                                                                                                     rme S
a
                                                                                                                          ?z9w -4
\   n                                                                                                                     c_a d
       *These systems must be qualified to the worst case environment in which they must function (including HELBs inside and outside containment).
      **These systems may see radiation from components in the recirculation path.
i

ATTACHMENT I STP FSAR                    ST-HL AE N" Appindix 7B                      PAGE 13 OF 3\
7B.8 TYPE E VARIABLES 7B.8.1   Introduction u.
Type E variables are defined in Section 7B.2.2.5. They are these variables that provide the control room operating staff with information to:
: 1. Monitor,the habitability of control room,
: 2. Monitor plant areas where access may be required to service equipment necessary to monitor or mitigate the consequence8 cf an accident,                                     40 )(
: 3. Ectinate the magnitude of release of radioactive materials through iden':1-                                 }
         -fied pathways and tenhd3 assess such releasesj awd                                                      )(
: 4. Mor.itor radiation levels and radioactivity in the environment surrounding the plant (via portable monitors).                                                                     A A                   A Key Type E variables are qualified to Category 2 requirements. Preferred backup Type E variables are qualified to Category 3 requirements. Table                                      f 7B.8-   lists the Type E variables.
7b.8-1                                 Amendment 40

ATTACHMENT i STP FSAR           ST-HL-AE PAGE 1:4 OF l@M Appendix 7B TABLE 7B.8g          C S/1%(d dF TYPE E VMIABLES
: 1. Control Rcom Habitability                                                 0# Y Control Room Radiation Lev e.\                                   E2            X
: 2. Post Accident Access 6 AreaRadiatio)n Post Accident Sampling Station                            E3*
Technical Support Center                                  E3*
Operational Support Center                                E3*
Cers 'tt f                                       y Emergency Operations F::ili:3                             E3*
Unit Vent Monitoring Station                              E3*
: 3. Release Pathways High Range Containment Radiation Level                           E2 Steamline Radiation Level & Relief Valve Status                  E2 Vent Unit Vent Radi.-no nrrrtivi:3 Level andp Flow E2          X li Condenser Vacuum Pump Radiation Level & Flowrate b '=
gt. ,, ,,c. 4 ,eu d a . Pu y w p stdvs E3 y 2, hf Exknus T                                                               y FHBg Vent Radiation Le.oe,I n                                          E2 Containment Sump & Atmospheric Sampling                          E3 S:::: rencr;;;; Radi :ic; Level i Elcud r Fler Ecte            -fd          Y Status                                                                           >.
Co..dar.;;;; Polich Fediatier le"-1 1 71 ~3 Da*-/Firr 50 ; ;     E3          >
Valut.,
Liquid Radwaste Radiation Level & F1. E:::/F1: 1 Status          E2          X Li j ui 4 bJ cuesTe Flow Ret                                     E3 TCE Drai; R;dictier Lavc.1 i ils S : /rls St : ;                 E2 '          )
* Category 3 per Regulatory Guide 1.97, Revision 3                                            )
7B.8-2                   Amendment 40

ATTACHMENT I STP FSAR         ST-HL-AE 1460 Appendix 7B        PAGE 76 0F M TABLE 7B.8-1 (Continued)
                                                       ].awer cass S)O!ARY df TfW E VJ0tf8tts
: 4. Site Environmental Radiation Level                             Ooi'18"1 Area Monitors (Portable)                                -
E3*
    ~
Meteorological Parameters                                   E3*
40
                ~
* Category 3 per Regulatory Guide 1.97, Revision 3 7B.8-3                      Amendment 40         1 1

ATTACHMENT /
ST-HL-AE- N30 STP FSAR                                PAGE % OF M AppIndix 7B TM LE Dsit.EM                             SECTION 7B.9
            ~'
IF8' T% M __7 E*I                         Table 7B.9-1
                                               -g y- - -- . r ne aio. - > ce r ;,,-4..
trv-irdir; E:ler*4-- rf r 2)                        .-
ar'iable                                                                   Type and Category Type                 Type           Type    Ty e     Type A                     B              C                E RCS Pressu e (Wide Range)                        16[                   1,2           1,i/    2 /
Wide Range T h t                                  1/                    1,$
                                                                                                     //
Wide Range T cold                                1 /                   1,V Wide Range S/G Level                             1/                        2/                2-Narrow Range S/G Level                           1-                    1,I.                  2/
Pressurizer Level                                   /                  1 #'                  2<
                                                                                                   ~
Containment Pressure                             1-                    1,2-          ~1,I-   2-                    40 Steamline Pressure                               1-                    1/                    2 RWST Level                                       1-                    1                     2<
Containment Water Level (WR) 1,I'          2       2 Containment Water Level          )                1.                    2             2.      2-Auxiliary Feedwater S rage Tank Level             1-                       <'                 2-Auxiliary Feedwate Flow                           1-                    1.                    2 High Range Cont ament Radiation Level             1.                    l,2-          2-               2.
S/G Blowdown adiation Level                       1                     2v                             2                -
Steamline adiation Level                          1.                    2,            2                2 ''
Core E t Temperature                              1                     1/            1 ,-
RCS ubcooling                                     1.                    1
                        ' utron Flux (Extended Range)                                          1 .                   2 Neutron Flux Startup Rate.                                             1                      2-i
                 $                                     ,$0' l
i 7B.9-1                                             Amendment 40                        I

ATTACHME     l                   )
ST-HL AE-l P STP FSAR                     PAGE 11 OF R\
Appindix 7B Table 7B.9-1 (Continued)                [
Summary of Variables and Categories (Excluding Selection of D-3)
Variable                                                Type and Cate cry Type  Type     Type       Type    Type A     B        C          D        E Containment Hydrogen    neentration                 1/       1 Reactor Vessel Water Le 1                           1./         ,/      2-Main Steamline Isolation V ve Status                2 - ?'              2 Main Steamline Bypass Valve S atus                  2-                  2.
Control Rod Position Ind.                                               3f Pressurizer Pressure                                                    2                 .
RCP Status                                                              2 ,.
40 Pressurizer Spray Valve Status                                          2' Containment Pressure (Extended Range)                        1,2 '
RCS Pressure (Extended Range)                 1     l        1-Containment Isolation Valve Status                           21 ~       2-Unit Vent Radiation Level                                    27                  26 RCS Sampling (Primary Coolant etivity)                       3.
                                                                                        ~
Fuel Handling Bldg. Radiati    Level                         2'                 2.          ,
Adjacent Building Area Ra ircion Level                       3-Site Environmental Rad tion Level                            3                   3-Pressurizer PORV Val e Status                       2.                  2 .-
Pressurizer PORV    ock Valve Status                                       .
Pressurizer Saf ty Valve Status                      2y                 2 Pressurizer ' ater Breaker Position                                     2/
Charging S stem Flow                                                    2 ['
n 78.9-2                      Amentiment 40

                         .                                                        ATTACHMENT /
ST-HL-AE. It/fo STP FSAR                   PAGE12 OF F1 Appendix 78 7;ble 7B.9-1 (Continued)                             e pg       8 Summary of Variables and Categories (Excluding Selection of D-3)
Variable                                                                    Type and C egory Type            Type       Typ           Type     Type A               B          C             D        E Letdown Flow                                                                                      2s VCT Level                                                                                         2-CVCS Valve Status                                                      _
2 *:'
RCP Seal Injection Flow                                                                           2 S/G Atmospheric.PORV Status                                                                       2 -c'    c_ '-
S/G Safety Valve Status                                                                           2         -
Main Feedwat;c Control Valve Status                                                               2-Main F/* .ontrol Bypass Valve Status                                                              2c-            40 Main F/W Irolation Valve Status                                                                   2 .; > '
Main Feedwater Flow               -                                                               2-S/G Blowdown Isolation Valve Stat s                                                               2 S/G Blowdown Sample Isolation           Ive Status                                                2
     '.uarging Pump Status                                                                             26 Main Feedvater Isolation alve Bypass Valve Status                                                                                      2 5-Auxiliary Feedwater solation Valve Status "7,                    . _ , ,.                        2 Containment Venti tion Damper Status Total HHSI Flow                                                                                   2..
Total LHSI F v                                                               .                     2 ECCS Valve' Status                                                                                2-ECCS Ac mulator Pressure                                                                           2 7B.9-3                                    Amendment 40
  ,s               --n--   ---       ,   - - - , _ ,            - - -
                                                                      -.Q   -        -         , - -      - -

ATTACHMENT I STP FSAR                   ST-HL.AE IV9 Appsndix 7B                  PAGE *hl OF 91 Table 7B.9-1 (Continued) 1 (O
Summary of Variables and Categories      90 (Excluding Selection of D-3)
Variable                                                  Type and Cate ory   ,
             .I        '
Type   Type     Type     Type     Type A      B        C        D        E Aux F/W Valve Status                                                    2[
AUX F/W Motor Driven Pu      Status                                     2.
Aux F/W Turbine Driven Pu      Status                                   2' Turbine Stop Valve Position                                             2 Turbine Covernor Valve Position                                         2 s' Containment Spray Flow                                                  2 .'J Containment Spray Pump Status                                           2 6'          40 Containment Spray System Valve Status                                   2</
RCB Fan Cooler Differential Pressure / Stat                             2#
CCW Pump Discharge Pressuru                                             2.
CCW Header Temperature                                                  2 CCW Surge Tank Level                                                    2 6.-
CCW Flow to ESF Components                                              2 '"
CCW Valve Status                                                        2..>
CCW Pump Status                                                         2' RHR Pump Status                                                         2.?
Essential Cooling Wat      System Flow                                     .'
Essential Cooling W er System Valve Status                              2' Essential Coolin     ater System Pump Status                            2(
RHR Heat-excha er Discharge Temp                                        2a RHR Flow                                                                2/'
7B.9-4                   Amendment 40

ATTACHMENT I ST HL-AE-14dO STP FSAR            PAGE 90 OF 8l Appendix 7B a(CL-                     ,
Table 7B.9-1 (Continued)                  8-Summary of Variables and Categories (Excluding Selection of D-3)
Variable                                                               Type and C egory Type    Type     Ty      Type     Type A       B        C       D        E RHR Valve Stat                                                                      2<
ESF Environment                                                                     2-SI Actuation Status                                                                 2.'
SI Pump Status                                                                      2- s '
SI Valve Status                           -           _
2 Containment Isolation Actuat n Status                                               2 ~#'
Boric Acid Transfer Pump Status                                                     2 Standby Power and Emergency Power our                                               2                     40 Status Other Safety Related Energy Source                                                  2.
tb Reactor Trip Breaker Position                                                       2.
Control Room Radiation                    --                                                 2 Acce , Area Radiation                                                                        3
  , FHJ Vent Radiation 2 ~
Meteorological Param ers                                                                     3-
                                                                                                            *~
Condenser Vacuum P p Effluent Radiogas                                                       3 Concentration Effluent Path    ow Rate
                                                          ^ ~ ~
Steam G erator Blowdown                                                                 3 Cond sate Polish                            , ,
3
                                                                                            +
L uid Radsaste                                                                          3-7B.9-5                        Amendment 40

r-ATTACHMEfi (
ST-HL-AE- 14 STP FSAR                                           PAGE 91 OF l Appendix 7B Table 7B.9-1 (Continued)                                 e       ( & re.-
Summary of Variables and Categories (Excluding Selection of D-3) f Variable                                                                  Type and Cate ry                   .
                ~
Type            Type                    Type      Type             Type A                B                      C         D                E TGB Drain                                                                                                  . 3' Unit Vent                                                                                                    2 >>
Condenser Vacuum Pump                                                                                        3 .. .'
Concentration From Liquid Pat ays        ,
2-     40 Steam Generator Blowdown Condensate Polish                                                                                           .:2 Liquid Radwaste                                                                                               2.gr TGB Drain                                                                                                     2 Effluent Pathway Status Steam Cenerator Blowdewn Valve Sta s                                                                          2 Condensate Polishing Valve Stat                                                                               2 Liquid Redwaste Valve Status                                                                                  2' TGB Drain Valve Status                                                                                        2 Condenser Vacuum Pump St tus                                                                                  2 i
Containment Sump & Atmosp ric Sampling                                                                             3 .'
l 1                 -
l 1
h 7B.9-6                                            Amendment 40
                                                        . - _ _ . , _ _ . - . - . . _ . ,               .- - . . .}}