ML20080E749
| ML20080E749 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/01/1983 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8309140065 | |
| Download: ML20080E749 (42) | |
Text
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September 1, 1983 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE. WI 53201 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U.S. NUCLEAR REGULATORY COMISSION Washington, D. C.
20555 Attention: Mr. D. G. Eisenhut, Director Division of Licensing
'Gentiemen:
DOCKETS 50-266 AN3 50-301 IMPLEMENTATION OF REGULATORY GUIDE 1.97 FOR EMERGENCY RESPONSE CAPABILITY POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Sapplement 1 to NUREG-0737 regarding " Requirements for Emergency Response Capability" requires that each licensee submit a report describing how it meets the requirements of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." In our letter to you dated April 15, 1983 regarding " Response to Generic Letter No. 82-33 Update to Schedule Requirements for. Emergency Response Capability" Wisconsin Electric committed to submit a report describing how it intends to meet the requirements of Type A, B, C, D, and E var-iables as described in Regulatory Guide 1.97 for Point Beach Nuclear Plant, Units 1 and 2 (PBNP).
The enclosure to this letter contains such a report including the schedule for planned instrument upgrades.
We believe that the planned instrumentation configuration and sampling capabilities at PBNP meet the intent of Regulatory Guide 1.97 regarding post-accident monitoring capability. All of the PBNP modifications associated with post-accident monitoring as described in the enclosure to this letter are expected to be completed no later than May 1985.
Equipment delivery delays, l
environmental qualification; test difficulties, or other problems may cause delays in this schedule. Wisconsin Electric is strongly committed, however, to maintaining this schedule.
We would be pleased to answer any questions you may have regarding this.information.
Very truly yours, C
dlh,v', / /
j C. W. Fay' Vice Pres dent-Nuclear Power Enclosure S
Copy to NRC Resident Inspector-g 8309140065 830901 1'
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ENCLOSURE IMPLEMENTATION OF REGULATORY GUIDE 1.97 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2-s 4
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Background
Revision 2 to' Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear. Power.Plantsito Assess Plant and Environs Conditions During.and Following an Accident" was isseed by the NRC in December 1980.
Wisconsin Electric performed a detsiled evaluation of Regulatory Guide 1.97-requirements in early 1981 so that implementation at PBNP could be conducted in a manner consistent with all of the other instrumentation backfits required _in response to NUREG-0737,
" Clarification of TMI Action Plan Requirements," and IE Bulletin 79-018, " Environ-mental Qualification of Class 1E Equipment." -Wisconsin Electric has undertaken a'significant effort to upgrade the post-accident monitoring instrumentation at P8MP including the planned installation or' replacement of 147 electronic pressure transmitters, 22' resistance temperature detectors, a completely new microprocessor-based radiation: monitoring system with 105 radiation detectors, 8 hydrogen
- analyzers; 8 sump-level transmitters, 4-safety valve position indicators, 6 high-range radiation monitors ~, 18 thermocouples, 156 core-exit thermocouple connectors, and an additional meteorological tower.
Associated cables, electrical penetra-tions,-instrument racks, indicators, and recorders were also planned for upgrading
-as required..In addition,' the instrument bus power supplies are being upgraded
~
with the addition of two new station batteries; two new Auxiliary Safety Instru-mentation Panels (ASIPs) are being installed in the control room, and two Safety
-Assessment System (SAS) and two~ Plant Process Computer System (PPCS) computers
~
-with'CRT displays in the control room are being added.
Improvements to the pcst accident sampling and analysis capabilities at PBNP were also planned to be consistent with. Regulatory Guide 1.97. requirements.. All of the above modifica-tions are expected to be' completed no later than May 1985.
Equipment delivery delays, environmental qualification test difficulties,.or other problems may cause delays in this! schedule. Wisconsin Electric".is strongly committed, how-ever, to: maintaining'this schedule.
- When modificatio'ns=at PBNP were initiated due to the requirements of tNUREG-0737 or IE Bulletin 79-01B, the requirements of Regulatory Guide 1.97 were factored into the modifications'from the very beginning.
This was done to reduce the long-term costs of these' modifications and to reduce the adverse impact on the safety and reliability or PBNP due to constant backfitting of l plant systems, operating procedures, training,'and maintenance.
Although a
- rajority of the above instrumentation modifications were initiated to meet the 1 requirements.of NUREG-0737 and IE Bulletin 79-01B, a number of modifications were initiated lin 1981 strictly to meet the requirements of Regulatory Guide 1.97.
These'. modifications' include the addition of new instrumentation for the contain-ment consisting of spray flow, atmosphere temperature, and sump water temperature; ithe' addition of redundant instrumentation for measurement of the Reactor Coolant System-loop temperatures, Steam Generator wide-range water levels, Condensate
' Storage Tank water levels,-and Refueling Water Storage Tank water levels; and the addition of. qualified instrumentation for Safety Injection Accumulator pressure land Service Water header pressure.
fCertain requirements of Regulatory Guide 1.97 were judged to be unneces-
- sary or unreasonable to backfit_in an operating plant. Justification is provided
- for those requirements to'which we take exception.. Wisconsin Electric believes that the planned final configuration for. instrumentation and sampling and analysis
- capabilities at PBNP. meets the intent of. Regulatory Guide 1.97 for post-accident monitoring capability. We believe that no additional modifications are required
- for the protection ~of the public health and safety.
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o
-i' S1ptembsr 1, 1983
=,.
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-II.
- Submittal, Supplement 1 to NUREG-0737, which was transmitted with Mr. D. G. Eisenhut's
' Generic Letter 82-33 dated December =17,1982, requested Wisconsin Electric to submit:a report for NRC: review describing how PBNP meets the requirements of Regulatory Guide 1.97.
Section 6.2 of Supplement _1 to NUREG-0737 recamends the submittal of a. table which includes information regarding~ instrument _ range,-
environmental _ qualification, seismic qualification, quality assurance, redun-
- dance and sensor location, power supply, location of display,' and schedule for t
l each iype A, B, C, 0,.& E variable shown'in Regulatory Guide 1.97 (Revision 2).
t
.This-enclosure provides the requested information and is consistent in organiza-tion with Table 2.(PWR Variables) of Regulatory Guide 1.97,- Revision 2 dated December 1980 with errata dated July 1981.
The schedule for each instrument-indicates when all of the Regulatory Guide 1.97 requirements as described in f
'this enclosure E l be met.
Deviations from the guidance in Regulatory Guide 1.97_(Revision 2 with errata) are indicated by.a darkened border around the associated parameter. _ Justification for each deviation is.provided in the 1
referenced footnotes 11ocated at the end.of this enclosure.
The general notes below:provio.i clarifications for each category:of information requested by Section_6.2 af Supplement 1-to NUREG-0737 with-the exception of instrument range-
. which is self-explanatory:
GENERAL NOTES
- 1.. - ' Sensor Locations
, The " sensor (s) _locatio'n(s)".information -requested in Section 6.2(e) of Supplement l'to NUREG-0737 is assumed to mean the application (e.g.,
" Reactor.' Coolant System Cold Leg Water Temp.") and not physical plant location. This'information-is provided in the column labeled " Variable."
2.
Environmental Qualification:
Instruments reported 'as environmentally qualified (i.e., marked "Yes" in the column labeled "Envir. Qual.") are planned to meet the provisions of NRC Rule 10 CFR 50.49 on the_ schedule submitted in Wisconsin Electric
. letter to Mr.:H. R. Denton dated May 20, 1983 regarding " Environmental
-Qualification of Electric Equipment Important to Safety:Within the Scope of.
10 CFR 50.49." As allowed.by 10 CFR 50.49(k), original PBNP instrumentation
.4 located in a potentially harsh accident environment has been environmentally qualified in accordance with the " DOR Guidelines." Equipment ordered after May 23, 1980' is planned for environmental qualification in accordance with Category I of.NUREG-0588_.(For Comment) (i.e., IEEE Std..323-1974) unless
- there are sound reasons to the contrary.
Consistent with 10 CFR 50.49 and
'NRC Generic Letter 82-09, PBNP is not required to environmentally qualify equipment: located in a. mild environment.
=
S2ptemb2r 1, 1983 s-3.
Seismic Qualification:
Instruments reported as seismically qualified (i.e., marked "Yes" in the column labeled "Seis. Qual.") are planned to meet the provisions of the PBNP FSAR, p. 7.2-9 (i.e., protection grade equipment is designed such that "for design basis earthquake (DBE), the equipment will not lose its capability to perform its design objective; namely, shut the plant down and/or maintain the unit in a safe shutdown condition") Typical equipment of this type orig-inally installed at PBNP was seismically tested by Westinghouse Electric Corporation as documented in WCAP-7397-L, " Topical Report Seismic Testing of Electrical and Control Equipment," dated January 1970.
No industry standards regarding seismic qualification existed at that time.
Equipment ordered after May 23, 1980 is planned for seismic qualification in accordance with Regulatory Guide 1.100 (i.e., IEEE Std. 344-1975) unless there are sound reasons to the contrary.
4.
Quality Assurance:
Instruments reported as meeting quality assurance requirements (i.e., marked "Yes" in the column labeled "QA") are planned to meet the provisions of the PBNP quality assurance program described in Section 1.8 of the PBNP FSAR.
This program, as described, satisfies the requirements of 10 CFR 50, Appendix B.
The implementation of specific Regulatory Guides and ANSI Standards.regarding quality assurance are consistent with the commitments of FSAR Section 1.8.
5.
Redundancy:
Instruments reported ~as meeting the single. failure criterion or redundancy requirements (i.e., marked "Yes" in the column labeled " Single Fail. Crit.")
are p.lanned for a minimum of two redundant electrically independent channels up to and including any isolation device.
The display may be a common multi pen recorder or dual' indicator.
The' redundant channels are also physically separated in accordance with the PBNP FSAR, p. 7.2-4 through
- 7.2-9.
PBNP meets the intent but not~all of the strict requirements for physical separation of redundant channels defined in Regulatory Guide 1.75.
Equipment ordered after May 23, 1980 was planned to meet the requirements of Regulatory Guide 1.75 as closely as practicable.
6.
Power Supply:
Instruments reported as meeting Class 1E power supply requirements (i.e.,
marked "1E" in the column labeled " Power Supply") are planned to be powered from either a 120 V. A.C. instrument bus or a 125 V. D.C. bus as described in the PBNP FSAR, p. 8.2-4 & 5.
At the present time the two main D.C.
safeguards trains at PBNP are battery backed. The power supplies for only two of the four A.C. instrument channels for each PBNP unit are presently battery-backed. Wisconsin Electric is undertaking a battery bus upgrade program including the addition of two new station batteries.
All A.C.
instrument channels will be battery-backed after the completion of this upgrade. The upgrade was planned to meet the physical separation criteria of Regulatory Guide 1.75 as closely as practicable.
Ssptembsr 1, 1983 7.
Disulay Location:
The display location is' indicated as control room board or instrument rack, Safety Assessment System (SAS) or Plant Process Computer System (PPCS),
Cathode Ray Tube (CRT), or Radiation Monitoring System (RMS) CRT.
- SAS, PPCS, and RMS CRTs will be located in the control room and will be acces-sible by the operator on demand.
The time histories of most parameters marked SAS, PPCS,oor RMS CRT are also available on demand by the operator.
The final display configuration of many variables is dependent on the installations of the new SAS and PPCS computers and associated CRTs and the installation of the= Auxiliary Safety Instrumentation Panels (ASIPs).
8.
Schedule:
The implementation schedule provided for each variable is the current best estimate of the completion of the final configuration for the associated instrument includino redundancy, final displays, power supplies, documenta-
-tion of qualification, and official turnover to operations.
The schedules are based on anticipated delivery and plant outage schedules.
Wisconsin Electric is strongly committed to maintaining these schedules.
Equipment
. delivery delays, environmental qualification test difficulties, or other problems, however, may cause' delays in these schedules beyond our reasonable control.
The final configuration for Clcss 1E power supply, display, qualification and quality assurance is dependent on the completion of the battery bus upgrade, SAS and PPCS computer installations, ASIP installations, and qualification upgrades and documentation. The schedule for final completion of those associated plant upgrades are consistent with separate schedule commitments.previously. submitted to the NRC Staff regarding those specific topics.
Most variables listed are already measured with fully operational instruments, however, the instruments are not considered com-plete in this enclosure until they meet all Regulatory Guide 1.97 require-mentslas described in this enclosure.
Note that instruments previously reported to the NRC staff,as meeting the requirements of NUREG-0737 or IE Bulletin 79-018 do not, in most cases, meet all of the Regulatory Guide 1.97 requirements as specified in the attached table.
For example, an instrument may be installed and operational, but the Class 1E power supply specified may not be met until the battery bus upgrade is completed or the final display configuration specified may not be completed until the ASIPs and/or SAS computers are installed and operational.
The schedules provided in
-this enclosure for meeting Regulatory Guide 1.97 requirements are not intended to change any previous commitment regarding NUREG-0737 or 10 CFR 50.49, whose requirements may be different.
Nevertheless, all final installations and upgrades described in this enclosure including instrument bus upgrades, SAS and PPCS computer installations, ASIP installations, and documentation of qualification are expected to be completed as indicated in the schedule column of this enclosure.
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September l,-1983 Page 1 IMPLEMENTATION OF REGULATORY GUIDE 1.97 4
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
- I.. Type A Variables:'.'those variables to be monitored that provide the primary information required to. permit the control room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events." Note:
these variables are plant-specific and based on review of the PBNP Emergency Operating ~
Procedures (EOPs) plus anticipated future changes to the E0Ps.
(5)
P1 ant Instrument.
Envir{2)Seis{3)
Power (6) Disp 1ay(7)
Purpose Variable (1)
Tag No.
Range Qual.
Qual.
QA(4) Crit. Supply Location Schedule (0) l Manual Shiftover Refueling 1&2-LT972 0.to 100%
@(a)-
Yes Yes Yes 1E.
Control December 1984 of the ECCS to the Water Storage & 973
.(Essentially Room R: circulation Mode To k Water Top.to Bottom)
Board; cn Low Level in Level SAS CRT the RWST Manual Selection RCS Wide-1&2-PT420, 0.to 3000-
'Yes Yes' Yes Yes 1E Control Decembe 1984 of High-Head or Range Pres-420A, & 420B psig Room 6
Low-Head ECCS sure Board; l
R: circulation SAS CRT Containment 1&2-PT945,
-6 to 54 Yes Yes Yes Yes 1E-Control December 1984 Narrow-Range 947, & 949 psig Room or Inter-(Narrow-Range)
Board; i
mediate Range 1&2-PT946, 0 to 90 psig SAS CRT Pressure 948, & 950 (Intermediate (Added to RCS Range)
Gauge Pressure)
Manual Trip of RCS Wide-1&2-PT420, O to 3000 Yes Yes Yes Yes 1E Control December 1984 R cctor Coolant Range Pres-420A, & 420B psig Room Pumps Based on sure Board; RCS Pressure SAS CRT Manual Shiftover Condensate LT4038 0 to 21 ft.
Yes Yes Yes Yes 1E Control-December 1984 4
of AFW Pump Suction Storage
& 4040 (Essentially Room to Service Water Tank (Tank A)
Top to Bottom)
Board; on Low Level in Level LT4039 &
SAS CRT the CSTs 4041 (Tank B)-
. _... ~
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l September.II1983
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~Page 2-c
- lHPLEMENTATION OF' REGULATORY-GUIDE 1.97<
r POINT BEACH NUCLEAR PLANT, UNITS 1_AND.2:
~
-I.
Type!A.: Variables'(cont.)'
t
. Single (5)7 Plant' Instrument.
Envir{2)3,$3{3)'
Fail. Power (6) Display (7)"
~
' Purpose
' Variable (1)
Tao No; Rance' Qual.
-Qual.
QA(4) Crit.' Supply-Location: Schedule (0).
i Manual Control of Steam. ~
462, & 463. -(Above:
Room _
1&2-LT461, O to 100%
Yes.
Yes' Yes.
Yes.
1E_
Control. -December.1984'
- .AFW Flow.to S/Gs:
Generator.
.to' Maintain Secon-Narrow-Range. (S/G A)
Tube Bundle /-
Board;.
i dary Heat: Sink for ' Water: Level. ' l&2-LT471, Below Feed-SAS CRT
.-RCS or to: Isolate
-(Primary) 472, & 473 Ring to Steam.
L Faulted S/G.
(S/G B)
Separators)
Auxiliary
- 1&2-FT4036
- O to 300 gpm YesT
.Yes Yes' No.
1E
. Control December 1984 i
- & 4037 (O to 150% ~
(Not'...
Room i
Flow to Steam
- Design Flow);
Required Board; i
(Backup Only)
Backup) 1
' Manual Control of Core Exit 1&2-TE1 50 to 1600*F_;YesII)
Yes(#) Yes Yes IE control December 1984-L 1RCS Pressure and Temperature
--thru 39=
Roon j
Temperature.for-
. (Core-Exit
- Board,
~
s.
Stsam Generator Thermocouples)
SAS CRi j.
-Tuba Rupture i
l Degrees'of 1&2-TM970 200*F Sub-
- )
Yes Yes Yes.-
1E Control December.1984 Reactor Cool- & 971 ant Subcooling-
. Cooling to Room i
50*F Superheat Board;
?
- 1&2-PT420A&B 0 to 3000 Yes Yes Yes Yes 1E-
(Pressure psig.
Input) 1&2-TE4500
$0 to 750*F Yes Yes Yes Yes 1E
& 451D~or l
1&2-TEl-39 (Tempegure Input) 2.
)
RCS Wide--
- 1&2-PT420,-
O to 3000 Yes Yes Yes Yes IE Control December 1984
}
Range Pres-420A, & 4208 psig Room s"*e Board; SAS CRT m
.y w -
September 1,1983 IMPLEMENTATION OF REGULATORY GUIDE 1.97
~
POINT BEACH NUCLEAR PLANT,-UNITS 1 AND 2
.I.
Type A. Variables (cont.)
Plant Instrument Envir(.2) Seis(3) bi"9I* 6 QA(4) Fail. Power Display (7)
. Purpose Variable (1)
' Tag No.
Range Qual.
Qual.
Crit. Supply Location Schedule (8)
Manual Control of Steam f1&2-PT468, 0 to 1400 Yes Yes Yes Yes lE Control December 1984 RCS Pressure and Generator 469, & 482 psig (0 to Room Temperature for Pressure (S/G A) 129% Design
. Board; Stcam Generator 1&2-PT478, Pressure)
SAS CRT Tube Rupture 479, & 483 (ccntinued)
-(S/G B)
Pressurizer 1&2-LT426, 0 to 100%
Yes Yes Yes
- cs lE Control December 1984 Water Level' 427, 428, & (Essentially Room 433 Top to Bottom)
Board;-
SAS CRT-Manual Termination Pressurizer 1&2-LT426, O to 100%
Yes Yes Yes Yes lE Control December 1984 cr Reinitiation of Water Level 427, 428, & (Essentially Room Scfsty Injection 433 Top to Bottom)-
Board; for Steam Generator SAS CRT Tubs Rupture RCS Wide-1&2-PT420, O to 3000 Yes Yes Yes Yes 1E
. Control December 1984 Range Pres-420A, & 4208 psig Room sure Board;
,_s SAS CRT Degrees of 1&2-TM970 200 F Sub-
[No["'
Yes Yes Yes lE Control December 1934 Reactor Cool- & 971 Cooling to Room 4
ant Subcooling 50*F Superheat Board; 1&2-PT420A&B 0 to 3000 Yes-Yes Yes Yes 1E SAS CRT (Pressure
.psig Input) 1&2-TE4500 50 to 750 F Yes Yes Yes Yes 1E
& 4510 or 1&2-TEl-39 (Tempe{gjure Input)
Auxiliary 1&2-FT4036 0 to 300 gpm Yes Yes Yes No lE Control December 1984 Feedwater
& 4037 (0 to 150%
(Not Room Flow to Steam Design Flow)
Required Board; Generators for SAS CRT (Backup Only)
Backup)
Steam Gener-1&2-LT461, 0 to 100%
Yes Yes Yes Yes 1E Control December 1984 ator Narrow-462, & 4G3 (Above Tube Room Range Water (S/G A)
Bundle /Below Board; Level 1&2-LT471, Feed Ring to SAS CRT (Primary) 472, & 473 Above Steam (S/G B)
Separators)
September 1, 1983' Page 4 IMPLEMENTATION OF REGULATORY GUIDE 1.97 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 II. Type B Variables:
"those variables that provide.information to indicate whether plant safety functions are being accomplished.
Plant safety functions are (1) reactivity control;-(2) core cooling; (3) maintaining reactor coolant system integrity, and (4) maintaining containment integrity (including radicactive effluent control)."
Single (5)
Plant Instrument Envir{2)Seisb3)
Fail. Power (6). Display (7).
- Purpose
. Variable (1)
Tag No.
Range Qual.
Qual.
QA(4) Crit. Supply Location Schedule (8) 6 c/s h D) hD)
Detcction and Neutron Flux 1&2-N31&32 1 to 10 Yes Yes 1E Control December 1984 Varification of (Source Range)
Room R:Ictivity Control Board;
-11
-3 1&2-N35&36 10 to 10 SAS CRT (Inter-Amps (SR and mediate IR together Range) coverapprgi-mately 10 to 100% rated power with one decade of overlap)
. Control Rod 1&2-R1 thru Full In to No No No No 1E Control Original i
Position 33 (Desig-Full.Out Room Plant nated Also by Board Design Core Position) hc)to N/A N/A N/A
~N/A N/A hd)
Original RCS Soluble None Boron Content (RCS Grab 6000+ ppm Plant Sample with Capability Analysis Cap-ability Only)
RCS Cold 1&2-TE450A 50 to 750*F Yes Yes Yes Yes IE Control December 1984 Leg Water
&C, 451A&C Room Temperature Board; SAS CRT 4
e
September 1, 1983
. IMPLEMENTATION OF REGULATORY GUIDE-1.97 POINT BEACH NUCLEAR PLANT, UNITS l'AND 2 II. Type B' Variables (contl)
(5)
Plant Instrument Envir{2)Seis{3)
Power (6) DisplayO)
Purpose Variable (1)
Tag No.
Range Qual.
Qual.
QA(4)' Crit. Supply Location ScheduleIO)
Det:ction and RCS Hot Leg 1&2-TE450B 50 to 750*F Yes Yes Yes Yes 1E Control December 1984 V2rification of Water Temper- &D, 451B&D Room C:ro. Cooling ature Board; SAS CRT RCS Cold Leg 1&2-TE450A 50 to 750*F Yes Yes Yes Yes 1E Control December 1984 Water Temper- &C, 451A&C
Control December 1984 420A, &
psig (Wide-Room 4208 Range)
Board; 1&2-PT429, 1700-2500 SAS CRT 430, 431, & psig (Pres-449 surizer Narrow -
Range)
II)
Yes(f) Yes Yes 1E Control December 1984 Core Exit 1&2-TE1 h
- F(*)
Yes Temperature thru 39 116004 Room (Core Exit Board; Thermocouples)
SAS CRT Reactor 1&2-LT494 0 to 125 ft.
Yes Yes Yes Yes 1E Control December 1984 Vessel Water & 495 (Essentially Room Level (Wide-Range) Top to Bottom)
Board; SAS CRT 1&2-LT496 0 to 45 ft.
& 497 (Essentially (Narrow-Top to Bottom Range)
Except Narrow-Range is Off-Scale with RCPs Running) i
September l,1983 Page 6 IMPLEMENTATION 0F REGULATORY GUIDE 1.97 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 II. Type B Variables (cont.)
Single (5)
Plant Instrument Envirb2)Seis{3)
Fail. Power (6)' Display (7)
Purpose Variable (1)
Tag No.'
Range QJal.
Qual..QA(4) Crit. Supply Location Schedule (8)
Detection and Degrees of 1&2-TM970 200'F Sub-
[No'"'
Yes Yes Yes 1E Control December 1984
.V:rification of Reactor Cool-'& 971 Cooling to Room C:rs Cooling ant Subcooling 50*F Superheat Board; (c ntinued) 1&2-PT420A&B 0 to 3000 Yes Yes Yes Yes 1E SAS CRT (Pressure psig Input) 1&2-TE450D & 50 to 750*F Yes Yes Yes Yes 1E 4510 or 1&2-TEl-39 (Tempe{gjure Input)
J' Det:ction and RCS Pressure 1&2-PT420, O to 3000 Yes Yes Yes Yes 1E Control December 1984
'V;rification of 420A, & 4208 psig-
~
Room R;rctor Coolant Board; System Integrity SAS CRT Containment 1&2-LT958 & 0 to 90" Yes Yes Yes Yes lE Control December 1984 Sump Water 959(Sump A) per Detector (Surp Room Level 1&2-LT960 with Overlap B.only)
Board;
.& 961 (Sump (Equivalent SAS CRT B - Main to Approximately Containment 0 to 350,000 Floor)
Gallons which Exceeds Maximum i
Available Inventory)
Containment 1&2-PT945,
-6 to 54 psig Yes Yes Yes Yes 1E Control December 1984 Pressure 947, & 949 (Narrow-Range)
Room (Design 1&2-PT946, 0 to 90 psig Board; Pressure is 948, & 950 (Intermediate-SAS CRT 60 psig)
Range)
,ms
,,s Det:ction and Containment See Table 1 ClosedorNotYesdgo["'Yes Yes
[Ngt lE Control March 1984 V:rification of Isolation Closed Room Centainment Isola-Valve Position Board tien and Integrity Containment 1&2-PT945,
-6 to 54 psig Yes Yes Yes Yes 1E Control December 1984 i
Pressure 947, & 949 (Narrew-Range)
Room i
(Design 1&2-PT946, O to 90 psig Board; i
Pressure is 948, & 950 (Intermediate-SAS CRT 60 psig)
Range) 1&2-PT968
-5 to 195 psig
& 969 (Wide-Range)
. ~.
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. September 1.1983
'.~
- Page y IMPLEMENTATION OF REGULATORY GUIDE 1.97-
-~
, POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
?III..TypeChariablesi- "those variables ~that provide'information to indicate the potential for being breached or."the
. actual breach of the barriers to fission product releases.
The barriers are (1) fuel cladding,,(2) primary coolant-pressure boundary, and (3) containment."
(5)~
-Plant
-Instrument-
' Envir(2)3,9,{3)'
Power (6[DisplayII) a hPurpose Variable (1)
Tag No.-
Range Quals Qual. QA(4) Crit'. Supply: -Location. Schedule ( )'
d Detection and Core Exit 1&2-TEl' 50 to Yes-
Yes
Yes
.Yes-IE-Control December.1984 VarifIcation.
. Temperature-thru 39 :
1600*f ')
f Room:
O cf-the Potential-
- (Core-Exit
_ Board; for or.the Actual Thermocouples)-
SAS CRT-
.Bratch of the Fuel-
.Citdding-Radioactivity RCS Grab SE-5 uCi/ml:
N/A' N/A
~N/A N/A N/A h
CAmplete-Concentration Samples and to 10 Ci/ml-H in Circulat-Analysis (Di. luted).
j ing Primary.
-(Equivalent to Coolant
-Approximately'
[
1E-6 to.1.SES"
- j' iTimestheTeg
' Spec. Limit) r Analysis of RCS Grab 0,to 1875 Kev N/A-N/A-N/A N/A N/A-N/A Complete Primary Cool-Samples
.(Minimum)-
i
? ant (Gamma-(Germanium-Spectrum for. Lithium (Ge-l-
Isotopic Li) Gamma' Analysis),
Radiation x
Detectors with
^
}-
Multi-channel-t T
l Spectrum
!~
Analyzer)
Dstection and-
-RCS Pressure 1&2-PT420, O to 3000
. Yes Yes Yes Yes-1E Control
. December 1984
~
i Vsrification of the 420A, & 4208 psig Room Patsntial for or (Wide-Range)
Board;
[
[
ths Actual Breach 1&2-PT429,-
of the Reactor.
430, 431, & psig I
Coolant Pressure 449 (Pressurizer B:undary Narrow-Range) j Containment 1&2-PT945,
-6 to 54 psig Yes Yes Yes Yes 1E Control December 1984 j
Pressure-947, & 949 (Narrow-Range)
Room (Design 1&2-PT946, 0-to 90 psig Board;
{
. Pressure 948, & 950 (Intermediate SAS CRT l
is 60 psig)
Range)
September 1,~1983 Page 8 IMPLEMENTATION OF REGULATORY GUIDE 1.97-POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
'III.
Type C Variables (cont.)
3 I (5)
QA(4) Fay 1fPower(6) Display (7)
' Plant Instrument Envir{2)Seis{3)
Purpose Variable (1)
Tag No.
Range Qual.
Qual.
IO)
Crit. Supply
. Location. Schedule Detection and Containment 1&2-LT958
'O to 90"
'Yes Yes Yes Yes
'1E Control December 1984' V rification of the Sump Water
& 959 (Sump per Detector (Sump Room Pstsntial for or Level A) with Overlap B only)
Board; the Actual. Breach 1&2-LT960 (Equivalent SAS CRT of the Reactor
& 961 (Sump to Approxi-Coolant Pressure B-Main mately 0 to Boundary (continued)
Containment 350,000 Gallons Floor)
Which Exceeds Maximum Avail-able Inventory)-
t Containment 1&2-RE126, I to 1E8 Yes Yes Yes Yes IE Control December 1984 Area 127, & 128-R/hr Gamma Room Radiation (High-Range)
Board; SAS CRT-1&2-RE102 0.1 to IE4 No No Yes No IE Control December 1984
& 107 mR/hr Gamma Room RMS CRT I
Effluent 1&2-RE215 0.01 to 100 No No~
Yes No IE-Control December 1984 Radioactivity- (Air Ejec-mR/hr Room RMS Noble Gas tor Gases)
(Ec uivalent CRT Effluent from to 5.72E-4F )j Condensor Air to 5.72 pCi/cc) i Removal System Exhaust RE225 0.01 to 100 No No Yes No lE Control December 1984-(Combined mR/hr (Equi-Room RMS Air Ejector valent to
.CRT Delay Duct 1.94E-4 to Low-Range) 1.94 pCi/cc)
RE226 0.01 to 100 No No Yes No 1E
. Control December 1984 (Combined R/hr (Equiva-Room RMS Air Ejector lent to 0.589 CRT Delay Duct to 5.89E3 High-Range) pCi/cc) 4
. September 1, 983-Page 9' IMPLEMENTATION OF REGULATORY GUIDE 1.97' POINT BEACH ^ NUCLEAR PLANT,-UNITS 1-AND 2-
'III. Type C Variables (cont.)'
(5)
Plant-Instrument
.Envir{2)Seis{3)
Power (6) Display (7)^
1 Purpose Variable (y)
Tag No.
~ Range Qual.
_ Qual.
QA(4) Crit. Supply Location
-Schedule (8)-
Detection and RCS Pressure 1&2-PT420, O to 3000
.Yes Yes Yes Yes lE Control December 1984
'Varification of
.420A, &
psig (Wide--
Roce the Potential for 4208 Range)
' Board; cr the Actual 1&2-PT429,
-1700 to 2500 SAS CRT Breach of the 430, 431, & psig (Pres-Ccntainment
.449 surizer Narrow-Range)
Containment 1&2-HA964, O to 10%
Yes.
Yes Yes Yes 1E Control December 1984 Hydrogen 965, 966,-
Room Concentration & 967-Board;.
SAS CRT Containment 1&2-PT945,
-6 to 54 psig Yes Yes Yes Yes lE Control December 1984 Pressure 947, &949 (Narrow-Range)
Room.
(Design 1&2-P!946, O to 90 psig Board; Pressure is 948, & 950 (Intermediate SAS CRT-60 psig)
Range) 1&2-PT968
-5.to 195 psig
& 969 (Wide-Range)
- ,_s Containment See Table 3 See Table.-3 [Nof"'-
No Yes No lE Control December 1984 Effluent (Containment Room RMS Radioactiv-Purge Exhaust)
CRT j
ity-Noble Gases from Identified Release Points 4
4 4
September 1,11983
'Page.10 LIMPLEMENTATION OF REGULATORY GUIDE 1.97 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 III' Type C Variables (cont.)
Plant
' Instrument-Envir{2)Seis[3) bfayl[(5) Power (6) Display (7)
Purpose Variable (1)
Tag No.
Range Qual.
_ ual.
QA(4) Crit. Supply Location Schedule (0)
Q
[5@h") -
No Yes. No 1E Control December 1984
'Det:ction and Radiation See Table 4 See Table 4 t
V;rification of Exposure Rate.
Room RMS the Potential for (Inside Build-CRT cr the Actual ings or Areas, Br:ach of the e.g., Auxiliary
'C:ntainment Building, Which
-(centinued)
Are in Direct Contact with Primary Contain-ment Where Penetrations and Hatches are Located)
Effluent See Table 3 See Table 3 No(a)
No Yes
'No 1E Coatrol December 1984 Radioactivity-
. loom EMS
~
Noble Gases CRT (From Buildings as Indicated Above) i i
1
~
{
~
- September 1,ii
~
1983 Page 11-
- IMPLEMENTATION OF REGULATORY GUIDE 1.97.
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2'
't IV.
. Type D Variables:<"Those variables that provide information to indicate the operation of individual safety.
a
' systems ~and other systems'important to safety."'
Plant' SInstrument
-Envir.(2)Seis{3) a1 r(6) Display (7).
j l Purpose Variable (1)
Tag'No.
Range-Qual.
Qual. - QA(4) Crit. Supply Location Schedule (8) i L
' Monitor" Operation: : RHR System -
1&2-FT626-O to 4000 gpa Yes Yes Yes No IE:
Control December 1984 l
i cf the Residual.
Flow ~
(0 to 2565-Room Hett Removal. System Design F1ow)-
Board;
)
,s 4
- RHR Heat 1&2-TE622 Lig "' to-
- Yes Yes
.Yes No IE Control December 1984
{
. Exchanger
& 623 350*F Room-4 Outlet (Individual-Board
~
1&2-TE627 100 to 400"F~ No -
-No No No IE Control-December 1984
.(Common
=;.
Room Outlet Temp.)
~ Board;-
n 1&2-TE630-SAS CRT'
[
(Common Inlet-q i
Temp.)
RHR Pump 1&2-PT628 & 0 to 600 psig_Yes Yes
-Yes No IE Control December 1984 ~
Discharge 629 (0 to 100%
- Room, j'
Pressure Design l Pres.
Board i
sure)
",_s
,_s
,s Monitor Operation Accumulator 1&2-LT934 & O to 14" Lilot
W . N Yes IE-Control Original i-of the Safety Tank Level 935 (Tank B)-(Equivalent Room
-Plant-Injtction Systems 1&2-LT938 & to a Design Board.
Design 939 (Tank A) Level Ranae I
I) of162 to 652B Accumulator-1&2-PT936 & 0 to 800 psig Yes.
Yes Yes Yes IE
. Control December 1984
}
Tank Pressure 937 (Tank B) (0 to.100%
Room-l 1&2-PT940 & Design Pres.
Board j
941 (Tank-A) sure)
,_s j-Accumulator 1&2-MOV841A Closed or
[jlg Yes Yes No IE Control Original Isolation (Tank A).
Open Room Plant-j Valve Posi-
'1&2-MOV841B Board Design-tion (Tank B) i t
a I
i
September 1 1983 Page 12 IMPLEMENTATION OF REGULATORY Gul0E 1.97-
' POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 IV.
Type D Variable (cont.)
(5)
Plant Instrument Envirf2)3,g,{3) 1 Power (6) DisplayO)
Purpose Variable (1)
Tag No.
Range Qual.
Qual. ~QA(4) Crit. Supply Location Schedule (8)
Monitor Operation Boric Acid 1&2-FIT 128 0 to 140 gpa h 9) h9) h9)No 1E Control December 1984 of the Safety Charging (Charging (0 to 111%
Room Inspection Systems Flow Line Flow)
~ Maximum Design Board; i
(ctntinued).-
Flow)
SAS CRT Flow in HPI 1&2-FT924 0 to 1500 g Yes Yes Yes No.
1E Control December 1984 System
& 925 (0 to LO W Room Design Flow)
Board HP Safety 1&2-PT922 0 to 2030 Yes Yes Yes No IE Control December 1984 Injection
& 923 psig (0 to Room Pump Discharge 111% Design Board Pressure Pressure)
Flow in LPI 1&2-FT626 0 to 4000 gpm Yes-Yes Yes No IE Control December 1984 System (Train A)
(0 to 256%
Room Design Flow)
Board 1&2-FT928 0 to 2000 (Train B) gpm (O to 130% Design Flow)
LP Safety 1&2-PT628 0 to 600 psig Yes Yes Yes No 1E Control December 1984 Injection
& 629 (0 to 100%
Room-(RHR) Pump Design Board Discharge Pressure)-
Pressure RHR Heat 1&2-TE622 & 50 to 350*F Yes Yes Yes No 1E Contral December 1984 Exchanger 623 Room Outlet Temp.
Board (ECCS Recir-I culation)
RHR Heat 1&2-TE3294 50 to 350*F Yes Yes Yes No 1E Control December 1984 Exchanger
& 3295 Room Inlet Temp.
Board (Containment Sump Water During ECCS Recirculation) i
SAptember 1)19831 IMPLEMENTATION OF~ REGULATORY GUIDE ~1.97
~
.-. Page 131 1.
^
POINT BEACH NUCLEAR _ PLANT, UNITS.1 AND'2-IV. bye'OVariables~(cont.)-
(5)
~ Plant Instrument' Envir{2)Seis(3)-
a]1 Power (6) DisplayI7)-'
Purpose-Vahiable(1)' Tag No.
Rance' Qual.
Qual.
QA(4) Crit. Supply, Location ' Schedule(8)
.(
Mon'itor Operation Boric Acid. LT102, 171, 0 to 100%
'Yes.
.Yes Yes-Yes-1E
' Control-December'1984 4-of.the Safety Storage Tank; &:189 (Tank.(Essentially ~
Room 7
Injection Systems
-(BAST)-'
. -B)-'1&2-LT106, Top to Board
..(centinued)
Water. Level
-172, & 190.
.Botton)-
<(Tanks A & C)-
,3 defueling-
-1&2-LT972 0 to.100%. g
.Yes Yes..Yes IE Control December 1984
-Water Storage & 973 (Essentially Room.
Tank (RWST).
Top.to-
-Board;
~
l Water Level Botton)
SAS CRT i - ; Monitoring of the-. Reactor 1&2-P1A&B, O to 1.2E3 No No No No-
-Non-1E Control Original N.,
.R actor Coolant
. Coolant' Pump' (Motor -
Design [J
[
System Status Current).
Amps
' Room
- Plant:
/t >;O 24
/
~
Board 4
/
Reactor Cool.1&2-FT411,
.O to 110%-
No -
Yes
,Yes Yes 1E Control.
December 1984 1
ant System-412, 413, Design Flow.
Room Loop Flow 414, 415, Board;.
f
['
& 416 SAS CRT Reactor Cool-1&2-PCV434 Closed-Inter-Yes Yes Yes Yes IE Control May 1985 N
ant System
& 435 mediate-Open Room
. g 3
4
' Code Safety
-(Valve -
l-Board; Valve Posi-Mounted SAS CRT 1
/
1i l
tion Magnetic Reed i
-s /'4
' Switches)-
e fA 7
\\ J 1
1 -
Pressurizer-1&2-PCV430.
Closed-Yes Yes Yes No IE Control December 1984 V
Power-
&431C-(Limit 0 pen Room l
Operated
. Switches)
Board;-
1 i
(PORV)
^
)(;
4 Relief Valve SAS CRf-Position i
i L
i 1
!.j;
September 1, 1983 IMPLEMENTATION OF REGULATORY GUIDE 1.97
. POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 IV.
Type D Variables (cont.)
Plant Instrument Envir(2) Seis(3) b"yI(5) Power (6) Display (7) pa l
_ Purpose
. Variable (y)
Tag No.
Range Qual.
Qual.
QA(4) Crit. Supply Location Schedule (8)
Monitoring of the.RCS Code 1&2-TE436 0 to 400*F No No No No 1E.
Control.
Original R2 actor Coolant Safety Valve & 437 (Code Room Plant System (cont.)
and Pres-Safeties)
Board Design surizer F9RV 1&2-TE438 Discharge (PORV Common
-Line Fluid Line)
Temperature Pressurizer-1&2-LT426 0 to 100%
Yes Yes Yes Yes 1E Control December 1984 Water Level 427, 428, & '(Essentially Room 433 Tcp to Botton)
Board; i
,_s Pressurizer 1&2-TIA&B Breakert
No No, No No Non-1E Control Original Heater Status (Non-Safe-Closed-Openl Room Plant guards Board Design Powered Backup Groups)
,_s 1&2-TIC &D
[Nd["'
Yes Yes No 1E (Safeguards-Powered Backup i
Groups) i 1&2-TIE (Safeguards-Powered Control Group)
Pressurizer 1&2-TE424 0 to 700 F No No No No 1E Control Original Temperature (Liquid Space)
Room Plant 1&2-TE425 Board Design (Steam Space)
RCS Pressure 1&2-PT420, O to 3000 Yes Yes Yes Yes IE Control December 1984 420A, &
psig (Wide-Room 420B Range)
Board; 1&2-PT429, 1700 to 2500 SAS CRT 430, 431, & psig (Pzr.-
449 Narrow-Range)
~'
4
' September 1, 1983 Page 15 IMPLEMENTATION'0F. REGULATORY GUIDE.1.97L
~
POINT BEACH NUCLEAR PLANT,.' UNITS 1 AND 2 IV.- Type D Variables (cont.)
Single (5).
~
' Plant Instrument Envir{2)Seis{3)
Fail. Power (6)l Display (7)
Purpose
. Variable (1)
Tag No.
Range Qual.
Qual.- QA(4) Crit.' Supply' Location ~ Schedule (8).
' Monitoring of the RCS 1&2-TEl-50 to -
Yes(I)
Yes(I)- Yes Yes lE Control' December 1984 R :ctor Coolant
. Temperature thru 39-ll600fF(*)
Room System (cont.).
'(Core-Exit-Board; Thermo-
-SAS CRT couples) 1&2-450A&C, -50 to 750'F Yes-Yes Yes Yes IE Control December 1984 and 451A&C Room-(Cold Leg, Board; Loop Wide-SAS CRT Range) 1&2-450B&D and 451B&D (Hot Leg Loop Wide-Range) i
,s_
Degrees.of 1&2-TM970 200'F tigf"'
Yes Yes Yes lE Control December 1984 Reactor Cool- & 971 Subcooling.
Room ant Subcool-to 50*F Super-Board; ing heat SAS CRT 1&2-PT420A&B 0 to 3000 Yes Yes Yes Yes 1E '-
(Pressure
,psig Input) 1&2-TE4500 50 to 750*F Yes Yes.
Yes Yes 1E
& 451D or 1&2-TEl-39 (Tempegure Input)
Pressurizer 1&2-LT442 0 to 100%
No No No No IE Control Original Relief Tank (Essentially Room Plant Water Level Top to Bottom)
Board Design Pressurizer 1&2-TE439 0 to,t No No No No IE Control Original QQQ3 )
Relief Tank Room Plant Temperature Board Design Pressurizer 1&2-PT440 0 to 100 No No No No IE Control December 1984
)
Relief Tank psig Room Pressure (0-100% Design Board i
Pressure) 4
L
.h'-
r y
- September '1,; 1983 Page 16'
' IMPLEMENTATION.OFLREGULATORY GUIDE 1.97 2*.-
~
POINT BEACH NUCLEAR. PLANT,. UNITS.,1 ANO.2-
- IV.y1 Type l:D: Variables (cont.)
. '. ( 5 ) -
Purpose a
Variable (1)-
Tag No.
.Ir.strumenti ~ Envir{2)3,4,{3)'
[ Power (6) Display (7)
Plant.
Range' Qual.
' Qual.- QA(4)ECrit.' Supply ' Location Schedule (8)>
17M6nitoring of the...ieactor.
Ll&2-LT494 & O td'125'ft. 'Yes' Yes Yes L Yes.' -1E'
' Control December 1984.
^
R uctor: Coolant
. Vessel Water :L495.(Wide- - '(Essentially
- Room LSystem (cont.)
- Level Range)
Top to Botton)
. Board; 1&2-LT496 0 to 45 ft.
- & 497
_(Essentially-
.(Narrow-Top to..Botton-Range)
.except Narrow.
-Range Offscale-y with RCPs..
Running)
. RCS Gas Vent 1&2-RC570-Open-Closed. Yes Yes.
Yes-No
- 1E Control.. December 1984
' Isolation
.A&B,-575 A&B,'
. Room-i'
-Valve Posi-and 580 A&B:
Board; tion-l-
}.
RCS Gas Vent 1&2-PT498 0 to 3000
-Yes Yes Yes. No IE-Control December-1984 System.
.psig-
- Room f
j_
. Pressure Board Monitoring the Steam.Gener.1&2-LT461, O to 100%
Yes Yes
- Yes Yes IE-Control December 1984 j
Operation of the ator Water 467., & 463 (Above Tube
~ Room-Secondary System -
Level (S/G A Bundle /Below Board;
}
(Stram Generator)
Narrow-Feed Ring to SAS CRT Range)
Above Steam l
-l&2-LT471, Separators) 472,~& 473
}
(S/G B
-Narrow-Range) i
{'
1
- 7
~
. il ' '
^
^.
ISeptember 1,'1983i
~
U Page.-17'
~ ~
3 IMPLEMENTATION OF REGULATORY GUIDE _1.97:
POINT BEACH NUCLEAR' PLANT, UNITS.1 AND 2 :
1
- d IV.': Type.D.Variablesi(cont.):-
(5)-
~
Plant <
Instrument Envir{2)3,j,{3)'
' Power (6)lDisplayI7)/
a gy).
< Purpose Variable
. Tag No.
~ Range-Qual.
Qual. -QA(4) Crit." Supply Location Schedul _e(8)~
Monitoring.thei iSteam Gener-1 1&2-LT460A&B 0 to.518" Yes Yes-Yes Yes:
1E=
Control
- December 1984 c
.Op2 ration of: the -
'ator: Water :
(S/G A Wide (Above Tube--
Room t
'Sec:ndary System._.. Level;(cont.) Range) sheet /Below
- Board; "j
.(St2am. Generator)1 1&2 LT470A&B Bottom of.
(c:ntinued)
(S/G B Wide.of Wrapper
< Range).
' Assembly to; 3
~Above Steam-l.
' Separators)-
m t
. Steam Gener-1&2-PT468, 0 to 1400 Yes:
.Yes.-
Yes Yes
.1 E -
Control.
December.1984 j.
_.ator Pres-
'469, & 482' ~psig-(0 to Room sure.(Lowest, (S/G-A)
--129% Design
- Board;,
i I
Safety Valve'c1&2-PT478, LPressure) '
SAS~CRT
-i i
Set at-479,l& 483.
-1085 psig).
-(S/G B)
+
Main Steam-1&2-FT464 & 0 to 4E6-Yes Yes Yes Yes JE Control December 1984-j.
Flow (for
. 465 (S/G A) lb/hr (0 to Room i
Safety / Relief 1&2-FT474 & 120% Design Board;-
1
-Valve Flow) 475 (S/G B) ' Flow)'
. Main Feed-1&2-FT466 &.0 to 4E6 No
.No.
Yes Yes 1E
. Control-Deceniher 1984 i
water flow?
467 (S/G A) ~1b/hr.(0 to
- Board;
}
1&2-FT476 &.120%~ Design Room:
[-
477 (S/G B) : Flow)'
SAS CRT:
Monitoring.the Auxiliary 1&2-FT4036. O to 300 gpm Yes-Yes Yes No IE Control December 1984 Op2 ration of:the Feedwater
.& 4037' (0 to 150%
Room Auxiliary Feed-Flow to Steam-Design. Flow)
Board; water System
,a 3
Auxiliary 1&2-FT4002
.O to 400 gpm g "'
Yes Yes No 1E Control December 1984 t
(rurbine-(0:to 100%
Room j-Pump Dis-
' Driven'
~ Design Flow)
Board charge _ Line Pumps) l Flow
.FT-4007 &
0 to 200 gpa j'
.4014 (Motor (0 to 100%
}'
Driven Pumps) Desian Flow) t I-i
{
- a September 1,,1983-
' IMPLEMENTATION DF: REGULATORY. GUIDE 1.975 POINT BEACH. NUCLEAR PLANT, UNITS'l'AND 2.
VI. Type D;Variab1's (cont.)'
c e
(5) cPlant;
- Instrument
- .
Envir{2)'.3,9,{3)l Power (6) Display (7).
a P'urpose; iVariable(y)
Tau No.
Rance' Qual.
Qual;- QA(4) Crit.iSupply Location Schedule (8) ha)
.No'
.No
- No 11 E, Control-. Original
11 iMonitoring the.
iAuxiliary 1&2-PT4005 0 to.1600-7 peration:of_the-Feedwater (Turbine-psig-
-Room' Plant 0
Auxiliary Fee'd-
' Pump Dis-Driven-Board Design.
i~
witarl System; charge Line.. Pumps) -
L(centinued)
Pressure PT4012 &
0 to 1600 4019 (Motor psig-
' Driven Pumps)'
,s
[ Auxiliary 1&2-PT4044
.O.to 100 psig M "'
Yes Yes No IE-Control.
December 1984 i
-(Turbine-Room i
' Pump. Suction iDriven Board.
-Line Pressure Pumps) 4
[
.PT4042.
0sto.100 psig
& 4043 (Motor-f Driven Pumps)-
1:
Condensate LT4038 &
.0 to 21 ft.
Yes Yes Yes Yes 1E Control
. December 1984 Storage Tank 4040 (Tank A)(Essentially Room.
i Water Level LT4039 &-
-Top to Bottom)
Board; j-
.(Primary 4041 (Tank B)
SAS CRT Source of-Water for AFW l
-Pumps
._v j
' Service Water PT2844 0 to 150 psig g "'
Yes Yes No 1E Control
. December 1984 Header. Pres- (North.
(0 to 150%
Room j
sure (Backup ~. Header)
Design Pres-
' Board Water Supply PT2845
'sure) to AFW)
(South Header)
L Monitoring.the Containment 1&2-FT962 & 0 to 1320 gpm Yes.
Yes Yes No 1E Control December 1984 l
1
. Op:: ration of.the
_. Spray Flow
& 963 (0.to 110%-
. Room j
-Centainment Design Flow)-
Board Cooling Systems 4
3 Containment 1&2-LT931 O to 100%
Yes Yes
-Yes No 1E Control December;1984 Spray Addi-(Essentially Room j
tive Tank Top to. Bottom)
Board Water Level 4
1 1
}
September 1 1983 Pcge_19' IMPLEMENTATION OF REGULATORY GUIDE 1.97
'IV.
Type'D Variables (cont.).
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (5)
Plant Instrument' Envir{2)Seis{3)
Power (6)' Display (7)
-Purpose -
Variable (1)
Tag No.
Range Qual.
Qual.
QA(4) Crit. Supply Location Schedule (0)'
1&2-TE3270, 40 to 320*F. h ")
h'V) hV)No Monitoring the Heat Removal 1E Control Original Op ration of the, by the Con-3272, 3274, Room Plant-C:ntainment.
tainment.
& 3276 (Con-
' Board" Design Cesling Systems Emergency tainment Fan (ctntinued)
Fan Coolers Cooler Air Outlet Temperature) 1&2-FS3225, 5 ft./sec. h") hV) h*)No 1E.
Control Original 3229, 3239, (Alarm Set-Room Plant
& 3240 point)
Board Design (Flow Switch (Alarm on Contain-only)'
ment Emergency Fan Cooler i
Air Outlet) 1&2-W1A1, Open-Closed ha)
Yes Yes No 1E Control Original' W181', W1C1, Room Plant
& W101 Board Design (Breaker Posi-tion for Con-tainment Emergency Fan Cooler Motors) 1&2-FT2896, Oto1200gpsh*)
h") hV)No 1E Control Original i
2898, 2900, (0 to 120%
Room Plant
& 2902 Design Flow)
Board Design 1
(Service Water-Flow-Return Line from Contain-ment Fan Cooler) 4
. September 1, 1983 Page 20-IMPLEMENTATION OF' REGULATORY GUIDE 1.97 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 IV. LType D Variables-(cont.)
(5)
S QA(4) Fay [~ Power (6) Display (7)
Plant Instrument Envir(2) Seis(3)
Purpose Variable (y)
Tag No.
Range Qual.
Qual.
Crit. Supply Location -Schedule (3)
Monitoring the Heat: Removal 1&2-TIS 2893,100*FIncreas-[Njf') [Njf')
[5kf')No IE' Control Original Operation of;the by the Con-2901, 2903, ing) (Alarm -
Room Plant' C ntainment tainment 2972 Setpoint)
Board Design
' Cooling Systems Emergency.
(Service (Alarm (c:ntinued)
Fan Coolers Water Return Only)
(continued)
Line From Containment Fan Cooler Temperature Alarm)
Containment 1&2-TE3292-50 to 350 F Yes Yes Yes Yes lE Control.
December 1984 Atmosphere
& 3293 Room Temperature Board;.
SAS CRT-Containment 1&2-TE3294
-50 to 350 F
-Yes.
Yes Yes Yes lE Control December 1984 Sump B Water & 3295 Room Temperature Board
- r. a
.a
.a M5nitoring the Charging Line 1&2-FIT 128 0 to 140 gpm [Nof"'
[Nof"' [No["' No lE Control December 1984 Opsration of.the Flow (0 to 127%
Room Chemical and Maximum Design Board; Volume Control Flow)
,. a
,. a System Letdown Line 1&2-FT134
.0 to 150 gpm Nj"'
g"' @"' No 1E Control December 1984 Flow (0 to 125%
Room Design Flow)
.a
.a
,a
_ Volume Con-1&2-LTil2 0 to l0WE l No
[Nof"' [No '"' Yes 1E Control December 1984 trol Tank
& 141 (Essentially Room i
Water Level Top to Bottom)
Board; SAS CRT (112 Only) i Boric Acid LT102, 171, O to 100%
-Yes Yes Yes Yes lE Contral December.1984 Storage Tank & 189 (Tank (Essentially Room j
(BAST) Water 8) 1&2-LT Top to Bottom)
Board Level 106, 172, &
190 (Tanks A&C)
Septenber'1. 1983
-Page!21'
- IMPLEMENTATION OF ' REGULATORY GUIDE 1.97 -
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2-IV.
Type D Variables (cont.)-
(5)'
Plant Instrument Envir(2)i Seis(3)
Power (6) Display (7) a Purpose.
Variable (1).
Tag No.
Range Qual..
Qual.
QA(4) Crit.-Supply. Location Schedule (8) cMonitoring the Component' 1&2-TE621'.,h")to
.- Ye s L Yes Yes No 1E Control
~ December.'1984 Operation of the-Cooling Water' 200*F
. Room C:oling Water Heat Exchanger Board Systems.
-0utlet Temper -
. ature '(Cooling -
Water to ECCS)
Component 1&2-FT619 0 to 8000 gpm Yes Yes Yes No 1E Control
. December 1984
. Cooling Water (0 to 110%
Room Flow '
Design Flow)'
Board
,_s Service Water.PT2844 0 to.150 psig g "'
.Yes Yes No 1E Control December 1984 Header Pres-.(North (0 to 150%
Room sure Header)
Design Pressure)
Board PT2845 (South Header)
Monitoring the High-Level LT1001-O to 100%..
No No No No 1E Boron Original tum. Operation of Radioactive (Waste (Essentially Recycle Plant
'Ridwaste Systems Liquid Tank. Holdup Top to Bottcm) and Waste Design.
Level Tank)
Disposal 4
Control Panel C59 j'
(Auxiliary Building)
Radioactive
- PT1037, 0 to 1 g No No No No 1E Boron
. Original Gas Decay 1038, & 1039 (0-to 10 Recycle
' Plant Tank Pressure
. Design and Waste Design Pressure)
Disposal Control Panel C59 (Auxiliary Building)
.s e..s c..s Vtntilation Systems Emergency See Table 2 Open-Closed ]!Lof3' Ng No 1E Control
. Original i
l Ventilation Room Plant i
Damper Position Board' Design i
i r
n
~
~>
- , ~ p.;
'Septemberfl,11983~
Page;22~
- 4 o
IMPLEMENTATION OF REGULATORY-GUIDE 1.97:
' POINT. BEACH NUCLEAR PLANT,-UNITS.1 AND 2; IIV.
Type D Variables (cont.)
-(5)'
o Plant
. Instrument LEnvir.( k eid3)
Power (6)lDisplayI7) 5 II)' -Tag No.
~ Range-Qual.
Qual. QA(4): Crit. Supply. Location: ISchedule(0)
Purpose Variable Moni_toring the-Station D05,7 06..
-100 to'.1000 h a)
Yesl Yes. No 1E' LControl- (Decembert1984=
~
Op; ration of the Batteries.
105, &'106.. Amps (Charge /
Room' i
Power Supplies
. Discharge Rate)
. Board (All Safety-Related-
'Open-Closed-
-Power Supplies are1
-(Battery Breaker r
Monitored as Listed Position)
.a j:
.Hara) 125 Volt.
D01, 02, 03 0 to 150 g"'
. Yes
.Yes.
No 1E Control December 1984.
i
-D.'C.
Buses-
& 04 Volts'D.C.
~
~'
Room 1
Open-Closed)
Board.
J
-(Battery Charger' 4
Supply Breake s),a L120. Volt 1&2-Y01,101, 0.to.150 g "'
Yes-Yes-No 1E-Contr01 December 1984-1A.C. Instru..
4 ment Buses
' 02,.102,.03, Volts A.C.
Room
?
.103,J04, &
Board'
- 104-4
.a i
4160 Volt-A.C. 1&2-A05 0 to.5300 g~
Yes-Yes No 1E Control.
Original-i Safeguards.
L& 06~
Volts:
' Room'
~Planti
}
Buses
' Board Design
,a
- i
-480 Volt A.C. 1&2-B03 0 to 600 g
<Yes Yes-No 1E.
Control.. Original Safeguards
& 04; Volts Room Plant Buses 0 to-400 Amps Board Design-
~(Safeguards-l Station Service
[
Transformer Output)-
.s j
Emergency.
G01 & 02
-52 to 68 HZ g "'
-Yes-
.Yes No 1E Control Original
- j Diesel 500 to 5000 Roomi
. Plant' i
' Generators Volts A. C.
Board'
' Design j
50 to 600 Amps
[
0 to 5000 Kw 1000 in to-l 4000 'out KVARS
^
[
'165 psig - Alars' Only:(s95% of
?:
Minimum Allowed l
Diesel' Air-Start-Pressure)
t September'l :1983
^
Page 23 IMPLEMENTATION OF' REGULATORY GUIDE 1.97-POINT BEACH NUCLEAR. PLANT,. UNITS 1 AND 2.
- IV. ' Type D VariablesI(cont.)
Plant Instrument
.Envir{2)3,$3{3) p,y)f(Loser (6) Display 5)
S.
l f7)
P Purpose'
' Variable (1)
Tag No.
. Range-Qual.
Qual.
QA(4) Crit. Supply: ' Location'. Schedule (8)
Operation of the:
Oil Day _
&.3934;- _
(Essentially.[5j(a)
Monitoring the.
- Diesel Fuel' LT & LS-3932 0 to 100%
.'ontrol; -Original Yes Yes' No 1E.
C Room Plant' Power Supplies Tank Level LS3930A&B Top to Bottom)'
Board Design-(All Safety-Related and 3931A&B
_s
,s
- Power Supplies are Instrument PI3001 Oto125psig[No
'No
[NpfNo N/A Control Original Monitored as-Listed Air Pressure (0.to 100%.
(Direct Room Plant Hera)(cont.)
Design Pressure)
Reading Board Design Gauge Only) i t
I l
I 3
t
l'-
September 1,i1983!
IMPLEMENTATION 0F REGULATORY: GUIDE'1.97 POINT BEACH NUCLEAR PLANT, UNITS 1~AND 2l
+V. 1 Type E. variables:
"those variables to be monitored as required for use in' determining the magnitude of the release of.; radioactive materials and continually assessing such releases."
4 (5).
. Plant.:
Instrument-Envir{2).Seis{3)
Power (6))DisplayN)
~ Purpose Variable (1)
Tag No'.
-Range Qual.
Qual.
QA(4) Crit. Supply-Location Schedule (8);
' Monitoring of Con-Containment; 1&2-RE126,-
1 to 1E8
~ ~ Yes.
.Yes.
Yes~ Yes-IE Control December 1984 tuinment Radiation Area Radia-1127, & 128.R/hr. Gamma
. Room for Release Assess-tion - High
[
ment and Emergency Range:
. Board;.
Plan Actuation
._a 1 Monitoring of Area. Area Radia-
-See Table 4. See Table.4 W ""'
_No Yes No
.lE Control December 1984 i
R:diation Inside tion Room.
j-
. Buildings or Areas' RMS'CRT Wh:re Access is-1-
.R: quired to Service 1
Equipment Important to Safety
,a l
Monitoring of Air-Special Par See Table.3 See Table 3 g "'
No Yes No 1E Control.
December 1984.
bsrne Radioactive ticulate Room Msterials Raleased Iodine Noble RMS CRT
~from Plant'for Gas-Systg)
R31 case Detection (SPINGS)
.m and Assessment Process Radi-1&2-RE231 1 to.lE4
- g ""'-
No Yes No 1E Control December 1984 ation Monitor & 232 mR/hr (
g). ~
Room 5
and Vent Flow lent to.15 RMS CRT j
'from. Steam to 1.5E3 i/cc)
Generator 1&2-FT464, O to 4E6 lb/hr Yes Yes Yes Yes 1E Control-. December 1984 i
Safety and 465,474,475 (0 to 120%
Room i
Atmospheric-(Steam Line Design Flow)
Board;-
l Dump Valves Flow)
i; i
1
}
1:
..m 3
September -1,: 1983 -
IMPLEMENTATI'ON OF REGULATORY GUIDE 1.97
- POINT BEACH NUCLEAR PLANT,- UNITS -1. AND "2-V.
. Type lE Variables-(cont.)
[(51 Power (6) Display )
P1 ant ~
Instrument-
'Envir.(2) 3,9,(3)
_. Variable (y)-
Tag No.
Range' Qual.
Qual.
QA(4) Crit. Supply-Location"~ Schedule (8)-
.g Purpose' i
-Monitoring:ofcAir, Particulatess, Grab Samples,1E-6 to IE2 N/A' N/A N/A
'N/A' - 'N/A' N/Ai
~ Complete i-Barne' Radioactive' Jand. Halogens 'from 'Isokin pCi/cc Materials Releasedfrom All'Iden. etic ~ Stack 0-to 6000 No
-No Yes No 1E Control-. December 1984 from Plant.for.
tified Release Sampling.Sys fpm-
' Room RMS
..Ralsase' Detection Points-(except tem with On- (Equivalent CRT
-cnd Assessment.
Steam Gener-
.. Site Analysis to O to
-(ccntinued)
'ator Safety
.-Capability 155+% Design 4-Valve and (Auxiliary Flow)
Atmospheric.
. Building and
' Steam Dump-
~ Drumming Area
. Valves) Samp-Vent Stacks)-
ling.with'On- -(Containment site Analysis. Purge Is' Iso-7 1 Capability' lated During:
E Power' Opera-)
f Monitoring of tion)-
Airborne Grab Samples :1E-9 to.1E-3 : N/A -
N/A N/A N/A N/A N/A Complete i
Environs Radiation Radiohalogens with OnsiteuCI/cc End Radioactivity and Particu-Analysis for Release Detec._1_ates
,m j
tion and Assessment Plant.and Portable IE-4 to uEF" N/A -
N/A N/A.
N/A. N/A N/A Complete a
Environs Radiation R/hr Gas
- )
. Radiation Survey 1E-3 to SE j
Meters Rad /hrI a
r Thermolum-1.0 mR to 1ES N/A N/A N/A N/A N/A N/A Complete iniscent R Gamma Dosimeters 1
(TLDs)
Plant and
. Grab Samples 0 to 1875 Kev N/A N/A N/A N/A N/A N/A Complete l
Environs (Germanium- (Minimum)
Radioactivity Lithium (Ge-Li)
}
(Isotopic.
Gamma Radia-l Analysis) tion Detectors with Multi-Channel Spec-trum Analyzer) i
.. ~
^ +,
- p Septemberf1,'1983
-IMPLEMENTATION 0F' REGULATORY. GUIDE 1.97 _
- Page 26
- -
' 2 2 POINT: BEACH. NUCLEAR PLANT,; UNITS 11AND 2-
!V. Type E, Variables'(cont.)
_ -(5)
Plant ~-
Instrumenti Envir{2) :3,$ 3{3):
Power (6) Display (7)
.VariabiM1)-
Tao No.
Range
~ Qual.
Qual.
QA(4) Crit.-Supply:
Location: Schedule (8) i t
-Purpose 7 MonitoringLof-Wind.
'MT1WDHI, l0-to.540" No No No-Yes Non-1E!.Contro1 December 1984 : -
f;
-Mettorological-Direction
.MT1WDLO,
-(Accuracy ofL Room..
Ccnditions for,
AMI2WD'-
LiS*, starting' PPCS CRTi p
R31 case' Assessment-threshold of' J
'0.6 aph,1 dis-tance' constant 1of'3.7 ft.,
i damping ratio L
of 0.4)
-+
Wind Speed:
-MT1WSHI.
,0 to 108. mph.No No No Yes
.Non-1E -Control December 1984
'MT1WSLO,
.(Accuracy of-Room
& MT2WS 1.15 mph,~
PPCS CRTi 1
starting;'
threshold.
1:
of 0.6 mph)',,,s j~
Estimation of MT1DT.
-10 to l11Q*ff ' ' 'No do No-No Non-1E Control December 1984 j
Atmospheric
-(Vertical (Interval of Room i
Stability Temperature.114-ft. on PPCS CRTL j
- Gradient) 150,ft. tower,'
accuracy of!
j 0.3*F)'
t
.MT1WDSD &
0:to 108", - No '
.No No Yes-Non-1E-Control-December 1984 MT2WDSD Room (Standard PPCS CRT
, Deviation of Wind Direction)-
i.
Accident Sampling Primary Gross Activ-SE-5 uCi/ml N/A N/A N/A N/A N/A-N/A Complete and Analysis Coolant ity
.to 10 Ci/ml i
.Crptbility On-Site and Sump (gg)
(Diluted)
-fcr Release Grab Samples Gamma Spec- 0 to 1875 kev N/A N/A N/A N/A N/A
.N/A-Complete-Assessment and
.trum (Ger-(Minimum) l' Verification nanium-Lithium l.
(Ge-Li) Gamma i
Radiation j
. Detectors with Multichannel
. Spectrum Analyzer)
t
' September 1,:1983:
P:ge.27:
.c IMPLEMENTATION OF REGULATORY GUIDE;1.97 POINT BEACH NUCLEAR PLANT, UNITS 1-AND 2
- V. -Type E Variables (cont.)
bf[yI(5)lfPower(6)' Display ()-
Plant Instrument Envir{2)Seis{3)
Purpose-Variable (1).. Tag No.
Range Qual.
Qual.
QA(4) Crit. Supply Location Schedule (0)
P' imary Boron
.[h](c)to N/A N/A.
.N/A N/A N/A N/A.
Complete Accident Sampling-r cnd Analysis Coolggg)and Content 601)0< nom
~
Ctpibility On-Site Sump Chloride L.1'""';to N/A N/A N/A N/A N/A N/A Complete for Release Grab Samples Content 20t. ppm Asssssment and
.(Cont.)-
Dissolved LlDt to N/A.
N/A N/A.
N/A N/A N/A Complete V:rification Hydrogen 2000+ cc/Kg a
(c ntinued)
(Primary-Coolant Only'
..,s
- Dissolved Nonetdd' N/A N/A
.N/A
.N/A.
N/A N/A Complete Oxygen pH 1 to 13 N/A N/A N/A N/A N/A N/A Complete Containment Hydrogen 0 to 10%,
N/A N/A' N/A-N/A N/A N/A Complete
~ ~~
Air Grab Content
..,s Samples Oxygen lNonefdd'
.N/A N/A N/A N/A-N/A N/A Complete Content Gamma 0 to 1875 kev N/A N/A N/A. N/A N/A N/A Complete
. Spectrum (Minimum)
(Isotopic (Germanium-Analysis)
Lithium (Ge-Li)-
1 Gamma Radiation
.. Detectors with
' Multichannel
' Spectrum Analyzer) l 1
4 s
+'
S:ptember 1, 1983
.a TABLE 1 CONTAINMENT ISOLATION VALVE POSITIONS
- Plant-
-Item. Tag No.
Description 1'
1&2-CV313 & 313A Reactor Coolant Pump Seal Return Line Isolation
'2.
1&2-CV371 & 371A-Reactor Coolant Letdown Line Isolation 3.
1&2-RC508-Reactor Makeup Water'Line to Pressurizer Relief Tank (PRT) Isolation 4.
1&2-RC538 & 539 Gas Analyzer Line from PRT Isolation 5.-
1&2-CC769 Component Cooling Water Return Line from Excess Letdown Heat Exchanger Isolation 6.
1&2-SI846
-Safety-Injection Accumulator Nitrogen Fill Isolation 7.
1&2-SV966A & 951*
Pressurizer Steam Space Sample Line Isolation 8.
-1&2-SV966B & 953"-
Pressurizer Liquid Space Sample Line Isolation 9.
1&2-SV966C & 955" Reactor Coolant Hot Leg Sample Line Isolation 10.
1&2-hL1003A&B
-Reactor Coolant Drain Tank (RCDT) Pump Suction Line Isolation-11.
1&2-CV1296 Auxiliary Charging;Line. Isolation
' 12.
1&2-WL1698 RCDT Pump' Suction fEom -19'3" Auxiliary Building Sump Isolation
' 13.
1&2-WL1721 RCDT_ Pump Common Suction Line Isolation 14.
1&2-WL1723'& 1728-Containment Sump A to -19'3" Auxiliary Building Sump Line Isolation 15.
L1&2-WL1786 & 1787-Vent-Header Line from RCDT Isolation 16.-
1&2-WL1789 & 1789 Gas Analyzer Line from RCDT Isolation
-17.
1&2-CV2042, 2045,-
Steam Generator Blowdown Line Isolation 5958, & 5959 18.
1&2-CV2083 & 2084' Steam Generator Sample Line_ Isolation 19.'
1&2-IA3047 & 3048 Instrument Air to Containment Supply Line Isolation
- 20.
1&2-CV3200A, B & C Containment Atmosphere R211 & 212 Radiation Monitor Supply and Exhaust Line Isolation 21.
1&2-HV3212, 3213, Containment Purge Supply and Exhaust Line Isolation 3244, & 3245 Indication-for 1&2-SV951, 953, and 955 are located on the sample ~ valve control panel in_the auxiliary building.
Sheet 1 of 1
.(*.
September 1, 1983
. TABLE 2 EMERGENCY-VENTILATION DAMPER-POSITIONS
- Plant Item tTao No.
Description
- 1.~
JCV3246 & 3247.
' Service Building Controlled Access' Area Exhaust Dampers 2.
LCV3248'& 3249l Auxiliary Building Stack Exhaust Dampers-
'3.
CV3258A1,.A2, B1,-
Auxiliary Building Carbon Filter Exhaust System
{.
'& B2 Dampers 14.
CV3265 &<3266 Auxiliary. Building Filter Fan Dampers 5.
CV4849A&B
. Computer' Room Air ~ Supply and Return Dampers-6.
-CV4849C.
Control Room Outside Air Intake Isolation Damper i-
~ 7.
CV48490&E' Computer Room and Control Room Smoke & Heat Ventilation Dampers:.
. 8.
CV4948F Control Room Return-Air. Damper-9.
- CV4850 Cable Spreading Room Outside' Air.-Intake Isolation
~
.10.
CV4850B&C Cable Spreading Room Smoke & Heat Ventilation and Return' Air. Dampers-111.-
CV4851A, B, & C.
Control-Room Emergency; Filter System Dampers 4-Sheet 1 of 1
. m.J
?
2 s e September 1, 1983.
TABLE 3-SPINGS
'Planti Tag No.
Item Range Unit 1 Containment Purge Exhaust SPING-4'(Field Unit 21) 1-RE-301 Beta Particulate 6.3E-12 to 2.4E-6 pCi/cc 1-RE-302 Alpha Particulate Particulate 1-RE-303 Iodine L1-RE-304B Iodine Background.
1.4E-11 to 3.82E-6 pCi/cc (Fixed Filter at 60 1pm for one hoar) 1-RE-305 Low Range Gas 1.0E-7 to 6.0E-2 pCi/cc 1-RE-3068
-Area Monitor (Low Range Gas (Equivalent Xe-133)
Background) 1-RE-307 Medium Range Gas 2.5E-2 t 4.0E2 pCi/cc 1-RE-3083 Medium Range Gas Background (Equivalent Xe-133) 1-RE-309 High Range Gas 1.0 to 1.0E5 pC1/cc (Equivalent Xe-133)
Unit 2 Containment Purge Exhaust SPING-4_(Field Unit 22) 2-RE-301 Beta' Particulate 6.3E-12 to 2.4E-6 pCi/cc 2-RE-302 Alpha Particulate Particulate 2-RE-303 Iodine 1.4E-11 to 3.82E-6 pCi/cc 2-RE-304B Iodine Background (Fixed Filter at 60 1pm for one hour) 2-RE-305 Low Range Gas 1.0E-7 to 6.0E-2 pC1/cc 2-RE-306B Area Monitor.(Low Range Gas (Equivalent Xe-133)
Background)-
2-RE-307 Medium Range Gas 2 SE-2 to 4.0E2 pCi/cc 2-RE-3088 Medium Range Gas Background (Equivalent Xe-133) 2-RE-309 High Range Gas 1.0 to 1.0E5 pCi/cc (Equivalent-Xe-133)
Auxiliary Building Exhaust SPING-4 (Field Unit 23)
RE-311
. Beta Particulate 6.3E-12 to 2.4E-6 pCi/cc
^
RE-312-Alpha Particulate Particulate
-RE-313 Iodine.
1.4E-11 to 3.82E-6 pCi/cc RE-314B-Iodine Background (Fixed Filter at 60 1pm for one hour)
- RE-315 Low Range Gas 1.0E-7 to 6.0E-2 pCi/cc
-RE-316B Area Monitor'(Low Range Gas (Equivalent Xe-133)
Background)
RE-317 Medium Range Gas 2.5E-2 to 4.0E2 pC1/cc
- RE-3188
~ Medium Range Gas Background (Equivalent Xe-133)
RE-319 High-Range Gas 1.0 to 1.0E5 pCi/cc (Equivalent Xe-133)
Sheet 1 of 2
a c
2.-
' ' C
' ^
September,1, 1983 TABLE 3--
SPINGS lPlanti.
__ Item, Tag No.'
p g
1 Drumming Area Venti SPING-3 (Field' Unit.24).-
RE-321 Beta Particulate-
- 6.3E-12 to 2.4E-6 pCi/cc-
. RE-322 '-
fAlpha Particulate Particulate RE-323
-lodine.
1.4E-11 to 3.82E-6 pCi/cc
'RE-3248, tIodine Background
- (Fixed Filter at 60 1pm for one hour)'
F:
1RE-325-Low Range Gas
. 1.0E-7 to 6.0E-2 pCi/cc
.RE-3268:
Area Monitor (Low Range Gas' (Equivalent Xe-133).
Background)
=RE-327-
-RE-3288-
_ Medium Range Gas.
2.5E-2 to 4.0;' pCi/cc Medium Range Gas' Background (Equivalent Xe-133) 4 i
4 e-I A
't 2
..m Sheet 2-of 2.
t s -,
m r.+.n.w-,r
,e--u.
,,.,.v.,
.w,.,,.ms,,,,.,
~,,c
.,- m - -,,,.,
,.n,
,,f,,,,ng-.
,,,,.,n.w,,,,-nga m.-,.w + a e n w e, ens
.,,-,n
.,,,w.
- } ;
~
a..
N
^
S:ptemb:;r -1,1983~
og
-TABLE 4' l1 AREA RADIATION MONITORS E
Plant-Tag No.'
Item
' Range *
~
O.1-lb4 mR/hr-
- RE-101 1C'ontrol' Room-E~
4
- 1 RE-102;
- Unit.1 Containment
. 0.1-10 mR/hr.
4
- '2-RE-102
' Unit 2 Containment 0.1-10 mR/hr-4
-RE-103-Radiochemistry Lab 0.1-10 mR/hr.
4 11-RE-104 '.
Unit l'Chargirg Pump Room 0.1-10 mR/hr
~
4 2-RE-1.04 -
-Unit 2 Charging Pump, Room
. 0.1-10 mR/hr 4
.. RE-105 -
' Spent Fuel Pit
- 0.1-10 -mR/hr-4
.1-RE.106-LUnit 1 Sampling ~ Room 0.1-10 mR/hr 4~
- 2-RE-106 = -
' Unit 2 Sampling Room
- 0.1-10 'mR/hr 4
1-RE-107
! Unit 1 Seal Table O.1-10 mR/hr 4
l2-RE-107.
Unit 2. Seal: Table'
. 0.1-10 mR/hr 4
. RE-.108.
Drumming Station
. 0.1-10 mR/hr 4
~ 1-RE-109.z Unit 1 Sample Line~
0.1-10 mR/hr RE-109:
Unit '2 Sa'mple Line 0.1-104 M/hr 4
RE-1105
. S. I. - Pump Room s-:
O.1-10 mR/hr RE-111 C-59 Panel 0.01-100'R/hr-
- RE,1_12 -
- Central Primary' Auxiliary Building 0.01-100R/hr-4 RE-113 Auxiliary Building Sump-0.1-10 sR/hr
-RE-114 CVCS Holdup Tank'
.0.01-100 R/hr RE-116
. Valve Gallery 0.01-100 R/hr 4
- 1-RE-134 Unit 1 Charging Pump Room High Range -1410 R/hr-4
.2-RE-134.
Unit'2 Charging Pump Room High Range 1-10 R/hr 4
lRE-135-Spent Fuel' Pit'High Range.
. 1-10 R/hr Sheet'1'of 2 g
35
- 4, pp w y v33-e s'g-i=g'vgg^ W W ry gg+"gs-'bw-m'5r"?'897
-cy-Wwm+--mve---vy-
'PB7ye-ywy yy
e e
s
- S:ptembar 1,1983
~ TABLE 4' AREA RADIATION MONITORS Plant' Tag No.
Item-Range
- 4 RE-136 Unit 1 Sampling Room High Range 1-10 R/hr 4
l2-RE-136-Unit 2 San.pling Room High Range 1-10 R/hr-4
~RE-140 S.I. Pump ~ Room High Range 1-10 R/hr
- Range is' based on expected post-accident radiation dose rates.
Two overlapping
~ detectors are'used where required to cover the. entire expected range.
Sheet 2 of 2
' en s : Ne' s
a
,ev,
,a,
, ~,, -,,,,,,,
w
<,.-a,,,-,-v,
, +
r-e
wa 1F00TNOTES
-IMPLEMENTATION'0F' REGULATORY GUIDE 1.97
~ POINT BEACH NUCLEAR PLANT, UNITS 1 AND-2 s
a.
This equip **nt'is: located in a mild environment as defined by 10 CFR 50.49.
-Therefore, consistent with NRC Generic Letter 8-09 and 10 CFR 50.49, envir-onnental qualification;is not required for this equipment (see General' Note:2).'.'This equipment is not in the scope of 10-CFR 50.49(b), as reported in our May 20,11983 letter _to Mr.' H..R._Denton regarding environmental-qualification.
~
t 4
~
' b.'
The source and intermediate range neutron flux monitors are not required for?LOCA/HELB ' mitigation.
Reactivity contro111s automatically achieved and n
maintained by reactor. scram and the injection of boric acid into the.RCS by i
the safety injection system following a postulated LOCA/HELB.
The control rod positions:are verified as an immediate action by the operator in the
' control roem before the' harsh environment could significantly degrade the.
2 L
rod position indication signols. The proper operation of the safety injec-tion system is' monitored and verified through the use of environmentally and seismically qualified ~ instrumentation.
The reactor scram and boration
- by the' safety: injection l system ensures reactor-core shutdown with significant
-margin under all postulated: conditions. The RCS soluable boron content can be verified by an_alysis of RCS' grab saeples,-which are taken using environmentally
~
and se.ismically _' qualified. valves.
The RCS soluable boron content is not
-expected to change rapidly,.if at all, following:the initial boration
'during the ECCS injection phase of an accident.-lTherefore, periodic analysis of RCS samples would detect any significant changes in boron concentration.
Therefore, control' rod' position indication'and analysis of RCS samples for boron are considered adequate to ensure reactor shutdown and environmental and seismic ~ qualification ofs the source andLintermediate range neutron flux monitors is'not1 required. These monitors are not within the scope of 110 CFR-50.49(b) as reported lin our Map 20, 1983 letter to Mr. H. R. Denton regarding: environmental qualificiation.
c.
A-lower range-limit of 0 ppm boron is not practicable to measure.
A lower
-limit of 20 ppm is' adequate since a difference in reactivity between a
' _' boron concentratio'n of-0 and 20 ppm in the reactor coolant is negligible.
Ld.
(The. automatic injection.of boric acid into the RCS by the safety injection system following a postulated LOCA/HELB is monitored and verified through
.the use of qualified instrumentation.
In _ addition, since all sources of water'for the safety _ injection system-(SI Accumulators, Boric Acid Storage Tanks,.and Refueling Water Storage Tanks) are required'by. Technical Specifi-cations to contain boric acid solution of a minimum concentration, the
' proper operation of the. safety. injection system ensuresian adequate boron
- concentration in the. reactor coolant to achieve and maintain the safe t
shutdown of the reactor core.
The RCS soluable boron content is not expected
-to change rapidly, if at'all, following the initial boration during the
'ECCS: injection'pnase of?an accident. Therefore,' periodic analysis of RCS
' samples would detect any significant changes in boron concentration.
' Instrumentation to continuously monitor RCS soluable boron concentration is
~
-.-~ _ - -
- ~ _..-.
~
H hk '
~
Laot required sinc'e periodic' analysis of RCS grab-samples is adequate for
~
/ verification of reactivity control.
~
4 l
,e._ >The T/C system has a recommended upper range temperature limit of-1600*F with-its stainless. steel sheathing and_No.:20 AWG' extension wire (ANSI i
-Standard MC196.1-1975,~ " Temperature-Measurement Thermocouples").
The ISA Type'K (Chromel-Alcmel)-T/Cs~themselves and the readout devices have the h
capability of indicating temperhtures of up to 2300*F or greater. The g
.1600*F upperflimitiis considered adequate however, since temperatures above l200*F indicate _inadeqaate core cooling.
f.
"The original'thermocouples (T/Cs).in the reactor vessel upper internais-
.cannot_-be replaced but can'be;qualifled by~ analysis..The connectors,
~
- cables, splices,-electrical penetration assemblies, and reference junctions are being replaced with new equipment qualified'in accordance with 10 CFR 50.49.
g.
Temperature -inputs 'are from either qualified RCS Hot Leg Loop RTDs (1&2-TE4500 s.&i4510) or qualified Core-Exit Thermocouples;(1&2-TEl-39).
Temperature
~
input.is selectable between loop:RTDs and core-exit T/Cs.
- h.
Consistent with NRC Generic. Letter 82-09.and 10 CFR 50.49, those containment
~
isolation valves located in a mild environment outside containment are not=
l required to be. environmentally. qualified.
The valve position indicators located.in a potentially harsh accident environment are being environmentally qualified in accordance with 10 CFR 50.49.
. i.'- 1The-indication on-each containment' isolation valve is not redundant; However, theRisolation ;itself is redundant-and is achieved by the use of redundant' containmentiisolation valves, ' design.of. the system for greater than containment design pressure or the.use of'normally shut isolation E
valves-or check valves \\in ~ accordance with the licensing basis of the plant.
- Therefore,"thefsingleifailure criteria for indication is essentially met by
. l redundant isolation capability.
'j.
The: Tech) Spec.limitis.. expressed <as:A=100/EpCi/gmwhere5=theaverage sum of the beta and gamma energies _per. disintegration in Mev and A is the specific activity. = Assuming that E is 1.5'Mev, which is a typical value for a PBNP Unit, then the specific ~ activity limit is approximately 67 pCi/gm
~
or 67 pCi/ml.
~
s k.
- Instrumentation to continuoi. sly monitor RCS radioactivity concentration is not required.' / Analysis of RCS grab samples, which will be taken using environmentally and= seismically qualified valves,-is adequate to detect the y
breach of:the fuel-cladding. - Periodic. samples and analyses are more than
- timely-enough to: detect any slow deterioration of the fuel cladding.
The
< Y, remote possibility of rapid breach of the fuel cladding would most likely
' result onlyifrom.an; inadequate. core cooling (ICC) event which would be
- etected by numerousfother diverse instruments.
In the event of approach d
to11CC, the:RCS sampling frequency.would'be appropriately increased to
-~detect' fuel ~ failures.
As'a diverse backup, an area radiation monitor in
~'
the sample. room could be used provided containment isolation has not.been
. initiated thus securing'RCS~ sample flow.
In the event of a LOCA, the containment radiation monitors could be used as a diverse backup for this purpose.
1
- E u...
.m,..,_...s.-o..,,_
..._..-,.mm--~m. -, -. - -,. - - - - - - -, * -. - - - - -.. - ~ - ~
,s
.~.
~
m s
e TheI etecthrs are currently strapped to a-pipe. :New. detectors are planned d ~
' 1.
ito.be mounted in a pipe;well to. increase the sensitivity.
The new range Lwill'be. determined when the'new detectors aretinstalled and-is expected to 1m coverjthearange renommended by Regulatory Guide 1.97.
La.i i sdiation exposure rate.is an ineffective means of detecting-the breach of R
containment.
Since other variables-(e.g., Auxiliary Building Exhaust
) Radioactivity):would be~used for this: purpose,1 the environmental.qualifica-tion of this instrument is.not required. - This instrument is not within the
- scope of.10 CFR.50.49(b);as reported.in our May 20, 1983 letter to Mr. H. R.
i;
'Denton regarding environmental qualification.
n
'n.
jThis value1(50*F) is the lowest:possible value expected for this variable lTherefore, this; range meets 1the intent of Regulatory Guide 1.97 and is
- adequate.for monitoring-system operation.
1:
o.
1The accumulator -level instruments are not required for mitigation of LOCA/HELB F
s
-since the: safety injection accuelators are passive devices.
The accumulator
~
. pressure instruments, which are qualified, could be used to derive an iequivalent accumulator. water : level. ; Therefore, the range, quality assurance,
+
environmental qualification,:and seismic qualification requirements of p-Regulatory Guide 1.97:for accumulator level are unnecessary.
. p.
This valve is normally, open with power administrative 1y removed (i.e.,
breaker' locked open)~from_the motor operator.
Since the closing of this valve is not required (for accident mitigation, environmental qualification of the valveipositionfindicatortis not required.
This valve is not within -
the scope of 10 CFR 50.49(b).as reported iniour~May 20, 1983 letter to Mr.LH. R. Denton:regarding environseqtal(qualification.
i.
,q.
The-charging pumps are'notiused for mitigation ~ of design-basis accidents.
i
~
- Therefore, environmental:and seismic qualification and quality assurance of
~
v the charging line flow instrument is not required.
Boric acid is injected'
.into the RCS during LOCA/HELB accident conditions using the safety injection
. system,swhich has qualified ~ flow' instruments.
The charging.linejflow~
i
.transmitterLis not within the scope of 10 CFR 50.49(b) as reported in our May 20, 1983 letter to Mr.
H.' R. Denton regarding environmental qualification.
l 4
r.
- The~ upper rangefof 107% of high~ pressure safety injection flow is adequate ato'monitorJthe expected range of; flow conditions.
The 107% is close to 1100 and is' adequate to determine pump runout flow rate in an accident.
!s.-
Pressurizer h' eaters.are not' required for mitigation of-design-basis accidents.
- Breaker positions for'the heater groups are'an adequate indication of heater status. ' Pressurizer temperature and pressure are also available as
~
-backup-indications'of heater-status.
^
DThis: upper range limit (300*F) is.close to the saturation temperature t.
(336*F);for the tank design pressure and rupture. disk release pressure of D100'psig.' 1This range is' adequate for. post-accident monitoring of this tank
- since' pressure can be used as a backup 'and no operator action is required for; accident mitigation based on this parameter.
n s
+'
t
-4 y
1 y 4+
--yv--
=ry v o o, -== e,4 c~,.~+-eav--,,r-e-y-- w v e-et e er, age,w+ w a. -t e-v-ee. ne w -sc ie w e y wo w.- s e-,
- nw = w w w w -,v w, w- =tw
-ww w
v e rw- +up,+
n re, + ww--e.-,3-me-+-
.xm-m
- u.1 Deleted vb
'The' containment atmosphere temperature RTDs (1&2-TE3292 and 3293) and containment prescure instruments are the primary. instruments used to non-E.itor heat" removal by the containment emergency. fan coolers. Thase instru-ments-seet-QA,~ qualification,7and single. failure requirements. 'Therefore, l qualification and QA on the backup instruments.are not required.
The backup instruments are :not within the scope'of 10 CFR 50.49(b) as reported
_in our May:20, 1983 letter to Mr. H. R.'lDenton regarding environmental qualification.
w.-
- The CVCS except'the BASTS are not_ required for mitigation of design-basis LOCA/HELB accidents. : RCS makeup-and boric acid injection is performed by the separate: safety injection system.' Therefore, qualification and QA on these instruments:are not required.
These instruments are'not within the scope of 10 CFR 50.49(b).as reported in our May 20, 1983 letter to Mr. H. R.
- Denton regarding environmental qualification'.
m ;x iThe ' upper. range limit of =100% of tank design pressure is adequate to monitor storage capacity as required by Regulatory Guide 1.97.
.need'to be changed.
~
This range does not 2
y.
This indication istnot required for mitigation of design-basis LOCA/HELB
- accidents.
The Radiation Monitoring System profides a backup indication if these~ dampers are out of. position.
Therefore, qualification and QA of thes'e damper position. indicators.'is. not required.
These position indicators are nottwithin the scope.of 10 CFR 50.49(b) as reported in our May 20, 1983 letter to Mr. H. R. Denton regarding environmental qualification.
, z.
Instrument air is not a safety-related system and is not required for
' design-basis LOCA/HELB mitigation. Therefore, quality assurance is not required for this-instrument.
d iaa.
Portabletsurvey metersfare th'e primary means'of-measuring radiation levels for personnel; access. Area radiation monitors are only used as an approxi-mation for planning purposes.
Area radiation m7nitors are not appropriate
[
ifor radioactivity release detection and assessment. Therefore, environmental
= qualification is not required. TheseEmonitorstare not within the scope of 10 CFR 50.49(b) as reported in'our.May 20,-1983 letter to Mr. H. R. Denton regarding environmental qualific' tion.
a
+
.~bb.
Locations-include containment purge exhaust vent, auxiliary building exhaust ivent,:and drumming area' vent. -AllJother identified' airborne radioactivity-release' points l(e.g., gas decaystank effluent; air. ejector effluent, steam generator' blowdown vent condensors','etc.),fexcept steam generator safety 1:g-
- andL atmosphere relief valve discharge,are released through 'these monitored y
- vent, paths (see PBNP FSAPu Figure 12-3).
Since containment purge is not
' allowed,at power and is'not planned to be used post-accident,1the contain-
. ment purge exhaust' vent SPINGs are not normally required for post-accident monitoring,'but would,cnevertheless'be available for operation in the event of'en' accident.
+
cc. I The' actual lower range limit of 0.15pC1/cc (0.10pci/cc is recommended by Kegulatory Guide 1.97) is judged to be adequate.
D p
-4 '
r A
+
i-- '
e p*s-g,yt-f-94
,e'=re-w' 'F r e #?e e P-T % + r--
gc:-
E9""i e'r =#w.6 *v ev C 9 y dr-1 4
e 4-a*"v wNF*'-2
- T w w e ' em F e 'e s ** e 9 *
-9 wwaw-a--T--***--9*W-w'N*e-w---ei'we"w'*-
- -'4'-t w-- v4-'
3 m
.4 s
r 4
dd.
The' detectors!are--located outside containment on theisteam line upstream of the main steam isolation' valves. These detectors are located'in a mild a
- environment except_for_the-extremely remote' possibility of a.stasm line
-break outside containment near.these, detectors. -In this case,.feedwater
.flowLto the faulted S/G will be isolated and'the only radioactive release
- will be'the: contents of~the S/G whose low-level radioactivity is known from~-
per. iodic : samples. Therefore,' environmental qualification of-these instru-
- mentstis not; required.
This instrument is not within the scope of 10 CFR 50.49(b)
'~
as reported in our-May 20,':1983 letter to'Mr.'H.lR. Denton regarding. environ-
, mental; qualification.
Lee..The. upper'rangeL11mit is adequate;since entrance to any High Radiation Area 2
-(i.e., >100 mR/hr) would be under tight administrative controls to preclude 4
p
- overexposure except in'an emergency.
ff. LThis range ~is based on an autoconvective'lapseJrate of approximately 7*F per 325 meters which is the maximum theoretical temperature gradient abeve
~ which;t'urbulent mixing occurs to equalize-the-temperatures.' Therefore,
~this range is judged to-be adequate.
gg. : Capability exists to sample the containment sump-through'the RHR sample
. lines 1when the ECCS is in the' recirculation mode. The capability exists to sample liquid. radioactive wastes. LThese wastes would. include collected wastes from ECCSfpump roonl drains and auxiliary building sumps.
hh. Analysis equipment.is avail 5ble from Wisconsin Electric's Laboratory Services Division, approximately one hundred miles from the plant site. The equipment would be transported to the plantisite fo'r analysis of-grab samples within J24 hours. - The sensitivity.of the analysis ls approximately 1 ppb or 0.1 ppm assuming.a'dtlution oflthe highly radioactive' sample-by a factor of 100.
~
iiii Thisl s the' minimum sensitivity for this measurement and-is adequate for i
~
.the purpose' stated.
jj. ~0xygen content.is not required to be measured at PBNP.
This was stated by the NRC Staff as documented in a letter'to Mr. C. W. Fay of Wisconsin Electric, dated June 30, 1982, regarding "NUREG-0737,. Item II.B.3, Post-(Accident Sampling System".
7 f
1
_4 >
~
I