ML20080F804
| ML20080F804 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/26/1983 |
| From: | Brown W CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20080F791 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8402130159 | |
| Download: ML20080F804 (120) | |
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l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT l
4 POSITION PAPER ON REGULATORY GUIDE 1.97 t DATE: [/.9,/h3 SUBMITTED BY: Ud_ m% M[ik --
RECOMMENDED BY: (( n#
APPROVED BY:
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REV. NO. SUBMITTED BY RECOMMENDED BY APPROVED BY DATE I N N $! b "": !s WYm _ k ./,f, 2$ D 8402130159 840201
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TABLF OF CONTENTS SECTION TITLE PAGE 1.0 Introduction 1 2.0 "Aneral Position Statement 1 3.0 Brunswick's Position Statement on RG 1.97 Positions 2 4.0 Plant Specific Position on Each Variable 8 l
l j 5.0 Abbreviations 37 6.0 References 38 l-Rev. 1 I
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LIST OF EFFECTIVE PAGES POSITION PAPER ON REGULATORY GUIDE 1.97 Page(s) Revision i 1 11 1 1-13 1 14a 1 14b 1
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I 1.0 I_NTRODUCTION I
This document states Brunswick's position on Regulatory Guide l.97, Revision 2, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident" (referred to in this document as RG 1.97). In assessing l
RG 1.97, Brunswick used information contained in ANS 4.5, BWROG Emergency Procedure Guidelines, Brunswick's FSAR, and assessment of RG 1.97 done by the BWROG. Section 2.0 provides Brunsw2ck's general position statement. Section 3.0 provides Brunswick's position statements on the generic RG 1.97 criteria. Section 4.0 details our position on each of the variables listed in Table 1 of RG 1.97.
" Agreement" or " Concurrence" means Brunswick will provide /has provided the recommended range and category stated in RG 1.97 unless noted.
2.0 GENERAL POSITION STATEMENT Brunswick concurs with the intent of RG 1.97, which is to ensure that necessary and sufficient instrumentation exists in a nuclear power station for assessing plant and environmental condition during and following an accident as required by 10CFR Part 50, Appendix A and General Design criteria 13, 19, and 64.
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- 3.0 BRUNSWICK'S POSITION STATEMENT ON RG 1.97 REGULATORY POSITIONS The position statements given below correspond to the referenced paragraphs in Section C, " REGULATORY POSITION" of RG 1.97.
Paragraph 1.1: Brunswick concurs with this definition.
Paragraph 1.2: Brunswick concurs with this definition.
Paragraph 1.3.la: Brunswick is an operating plant licensed prior to RG 1.89, " Qualification of Class 1E Equipment for Nuclear Power Plants". Brunswick will commit to ensuring environmental qualification as required l- by NUREG-0588 where applicable and Memorandum and
- I Order CLI-80-21. Additionally, Brunswick will only qualify equipment located in a harsh environment to these requirements. Thus equipment forming part of an instrumentation loop I which is located in a mild environment may not be qualified by testing.
Seismic qualification of existing equipment will be in accordance with Brunswick's FSAR for the original plant design. New equipment will be seismically qualified in accordance with IEEE-344-75. An isolation device will be provided between Jafety and non-safety portion of loops where engineering analysis requires its use, j Rev. 1
t 3.0 BRUNSWICK'S POSITION STATEMENT ON RC 1.97 REGULATORY POSITIONS
( Cont'd)
Paragraph 1.3.lb: A third channel of instrumentation for a Category 1 variable will be provided if a failure of one accident monitoring channel results in information ambiguity that would lead operators
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to defeat or fail to accomplish a required safety function, and if one of the following measures cannot be done:
- 1. Cross-checking with an independent channel that monitors a different variable bearing a known relationship to the failed monitoring channel.
- 2. . Perturbing the measured variable to determine the failed channel by observing the response on each instrument.
- 3. Using portable instrumentation to' validate correct channel.
Category 1 instrumentation channels shall be electrically divisionalized and handled in accordance with Brunswick's FSAR design requirements for divisionalized channels and circuits. Generally, Brunswick is designed to IEEE-279-1971.
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m -4 @ 4 een b 6 3.0 BRUNSWICK'S POSITION STATEMENT ON RG. 1.97 REGULATORY POSITIONS (Cont'd)
Paragraph 1.3.le: All Category 1 instrument channels shall be powered by plant emergency power sources designed in accordance with Brunswick's FSAR criteria and commitments.
Paragraph 1.3.1d: Brunswick concurs.
Paragraph 1.3.le: The quality assurance requirements invoked for the currently installed equipment were the Corporate Quality Assurance Program in effect at the time of purchase.' As part of the implementation of this Regulatory Guide, Brunswick will ensure that the equipment associated with Category 1 instrument channels are on the plant's Q-List such that the current Brunswick Quality. Assurance Program requirements will be invoked for future procurement, maintenance, and design change activities. Adherence to the requirements of the regulatory guides listed in this paragraph will be done if they are in the Brunswick QA program commitments. Refer to letter OQA-81-026 addressed to Mr. Eisenhut for details on the Brunswick QA program.
Paragraph 1.3.lf: Brunswick concurs with this position.
Paragraph 1.3.1g: . Brunswick concurs with this position.
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- 3.0 BRUNSWICK'S POSITION STATEMENT ON RG 1.97 REGULATORY POSITIONS (Cont'd)
Paragraph 1.3.2a: Brunswick's position on these criteria for Category 2 instruments are the same as given for paragraph 1.3.la above. Instruments that are not part of a safety-related system will not be seismically qualified unless Brunswick's FSAR invokes seismic requirements for the associated system.
Paragraph 1.3.2b: . Brunswick concurs with this position.
Paragraph 1.3.2c: Brunswick concurs with this position.
' Paragraph 1.3.2d: Brunswick's position on quality assurance requirements for category 2 safety-related instruments is the same as stated for paragraph 1^.3.le above. For non-safety related category 2 instruments the need for quality assurance requirements will be evaluated on a case-by-case basis. In general, quality assurance program requirements will not be imposed on non-safety related .
Category 2 instruments.
Paragraph 1.3.2e: Brunswick concurs with this position.
Paragraph 1.3.2f Brunswick concurs with this position.
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3.0 BRUNSWICK'S POSITION STATEMENT ON llc 1.97 REGULATORY POSITIONS (Cont'd)
Paragraph 1.3.3a: Brunswick concurs vith this position with the under-standing that environmental qualification testing is not necessary in selecting equipment for the service environment.
Paragraph 1.3.3b Brunswick concurs with this position.
Paragraph 1.4.a: Isolation devices will be provided between monitoring instrument channel and other user circuit only if the other circuit is designed to less stringent requirements, and engineering analysis requires its use.
Paragraph 1.4.b: Brunswick believes the identification of instruments for post-accident monitoring , falls into the realm of h aan factors engineering and must take into consideration all current activities such as control board review, new emergency guidelines and procedures. By incorporating these activities and RG 1.97 into an integrated project (SECY 82-111) the NRC has ensured that human factors engineering and integration is achieved. Brunswick will not commit to labeling the instruments but will develop a philosophy regarding instrument channel identification as part of the SECY-82-111 project. We believe this meets the intent of the guideline position.
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3.0 BRUNSWICK'S POSITION STATEMENT ON RG 1.97 REGULATORY POSITIONS (Cont'd)
Paragraph 1.5.a: Servicing, testing, and calibration procedures will be established and performed on a frequency necessary to maintain instrumentation capability. The frequency of servicing, testing, and calibration will be established from equipment experience data. The capability to service, test and calibrate the instruments during plant operdtic,n will be provided where necessary and feasible to do so.
Paragraph 1.5.b: Brunswick concurs with this position.
Paragraph 1.5.c: The utilization of design features such,as locked cabinets and seals to allow establistaent of controlled access to equipment setpoint, calibratica and other adjustments is not feasible at Brunswick.
Brunswick does not usually endorse such design considerations, but relies on procedure controls and personnel training. ,
Paragraph 1.5.d: Brunswick concurs with this position.
Paragraph 1.5.e: Brunswick concurs with this position.
Paragraph 1.5.f: Brunswick generally concurs with this position. How-ever, several exceptions are specified in Section 4.0.
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3.0 BRUNSWICK'S POSITION STATEMENT ON RC 1.97 REGULATORY POSITIONS (Cont'd) .
Paragraph 1.5.h: Periodic checking, testing, calibration and calibra-tion verification for protection instrumentation is in accordance with IEEE-338-1971, " Trial - Use Criteria for the Periodic Testing of Nuclear Power Generating Stations Protective Systems."
Paragraph 1.6: Brunswick's specific position on each variable is given in Section 4.0.
Regulatory Guide Section C.2 Paragraphs 2.1, 2.2, 2.3 and 2.4: Brunswick concurs with these positions.
Paragraph 2.5: Brunswick's position is outlined in our positions stated for paragraphs 1.3.la through 1.3.3b, 1.4a, 1.4b and 1.6.
4.0 PLANT-SPECIPIC POSITION ON EACH VARIABLE 4.1 Plant-Specific variables Considered by Brunswick to be Type A RG 1.97 defines Type A variables as "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 Rev. 1
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4.0 PLANT-SPECIFIC POSITON ON EACH VARIABLE (Cont'd) 4.1- Plant-Specific Variables Considered by Brunswick to be Type A (Cont'd) no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis events". Primary information is defined by RC 1.97 as "information that is essential for the direct accomplishment of the specified safsty functions."- (Variables associated with contingency actions that may be identified in written procedures are excluded from this definition of primary information.) The following paragraphs discuss each Type A variable by designating the safety function (s), operator action (s), and giving a measurement range for the variable. All Type A variables are category one and have been or will be provided at BrunswicN.
4.1.1 Variable A1 - RPV Pressure The RPV Pressure gives the information needed for the operator to maintain core cooling and reactor coolant system integrity. Operator action calls for depressurizing the RPV to maintain a safe cooldown rate by any of,several systems, such as HPCI, RCIC, ADS, and RWCU. The operator can also manually open one SRV to reduce pressure to below the SRV setpoint if any SRV is cycling. The range Rev.1
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.1.1 Variable Al - RPV Pressure recommended for this variable is 0 to 1500 psig in accordance with FSAR Section 5.2.2.2 and FSAR Table 7.5.1-1.
4.1.2 variable A2-RPV Water Level The RPV Water Level gives the information needed by the operator to restore and maintain RPV water level. The range recommended for this variable is -180 to +295 inches of water. The installed range will meet or exceed the recommended range.
4.1.3 Variable A3 - Suppression Pool Water Temperature Suppression Pool Water temperature gives the information needed by the operator to maintain containment integrity and reactor coolant system integrity. Operator actions are: Operate available suppression pool cooling system when the suppression pool temperature exceeds the normal operating limit, maintain RPV pressure at a reduced pressure if the suppression pool temperature cannot be maintained below the heat capabity temperature limit, and attempt to close any stuck open relief valve. The recommended range for this variable is 30 0 to -
2300 F. The installed range will meet or exceed the recommended range.
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4.0 PLANT-SPFCIFIC POSITION ON EACH VARIABLE (Cont'd) 4.1 Plant-Specific Variables Considered by Brunswick to be Type A (Cont'd) 4.1.4 variable A4 - Suppression Pool Water Level Suppression pool water level provides information necessary for the operator to maintain containment integrity.
Operator action calls for maintaining suppression pool water level within normal operating limits. If the suppression pool water level cannot be maintained below the suppression pool load limit, the operator is to maintain the RPV pressure below its corresponding limit. The range will be approximately minus' ten feet, which is the mid-plane of the lowest ECCS suction line to a position six feet above normal water level. This range follows from NUREG-0737 Item II.F.1, Attachment 5.
4.1.5 Variable A5 - Drywell Pressure Drywell pressure provides information necessary for the operator to maintain containment and reactor coolant system integrities. Operation action is to control primary containment pressure by containment pressure control systems. A range of minus 5 to plus 245 psig is provided and is in accordance with NUREG-0578. See PM 80-025, 026.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.1 Plant-Specific Variables Considered by Brunswick to be Type A 4.1.6 Variable A6 - Drywell Temperature Drywell temperature provides information necessary for the operator to maintain containment and reactor coolant system integrities. Operator action is to operate the drywell cooling system and those systems necessary to compensate reactor water level. The range recommended for this variable is 400 to 4400F. See Brunswick's FSAR section 6.2.1.1.1, page 6.2.1-4.
4.1.7 Variable A7 - Suppression Pool Pressure The Suppression Pool Pressure gives the information needed by the operator to maintain containment and reactor coolant system integrities. The operator uses this information along with drywell temperature and suppression pool temperature to determine when to initiate the suppression pool and drywell sprays. A suitable range for this variable is minus 5 to plus 245 psig.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.1.8 Variable A8 - Drywell and Suppression Pool Hydrogen, Oxygen Concentration Containment Hydrogen and Oxygen concentrations provide information necessary for the operator to maintain containment integrity. Operator action is to initiate the combustible gas control system in the Containment Atmosphere Dilution (CAD) system in the Brunswick design.
The ranges for these variables will meet or exceed the requirements of RG 1.97.
4.2. Brunswick's Position on RG 1.97 Type B variables RG 1.97 defines Type B variables as those that provide "information about the accomplishment of plant safety functiens". Key variables under type B are those variables which most directly indicate the accomplishment of a safety function.
Each variable is discussed in the following paragraphs and where this variable is covered under another variable type, it is indicated.
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, 3 4.0 PLAltT-SPECIFIC POSITI0tt Gi EACH VARIABLE 4.2 Brunswick's Position on RC 1.97 Type B variables 4.2.1 variable B1 - Neutron Flux The worst case scenario in wt'.ich neutron flux monitoring would be useful for post-accident monitoring consists of a failure of the control rods to insert (completely or partially) and operator actuation of the standby liquid control system. (If all rods insert, suberiticality is not a factor.) A failure of the control rod drive is not postulated to occur concurrently with a LOCA event. Based on the above scenario this environment is not one.in which the neutron monitoring system would be readered inoperable and environmental qualification is not necessary. This position is consistent with Q.12 and A.12 in Supplement No.
While neutron flux is a key variable for measuring reactivity control, the degree to which this variable is important to safety is another consideration. There is little probability that there would be, simultaneously, a need for this measurement (in terms of operator action to be taken) and an accident environment in which the neutron
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.4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) s; 4.2 Brunswick's Position on RG 1.97 Type B variables 1
4.2.1 - Variable B1 - Neutron Flux ' (Cont'd) monitoring system (NMS) would be rendered inoperable, I Additionally, thw large number of detectors that are driven into the core soon after shutdown makes it highly probable that one or more of the existing NMS detectors will be inserted and functioning. In light of the regulatory guide's graded approach to importance to safety and our position that this variable is less critical than others, l
we believe a designation as Category 2 is more appropriate and meets the intent of the regulatory guide. ,
4.2.2 Variable B2 - Control Rod Position 1
i Brunswick is in agreement with RG 1.97 and indication is f
l provided to monitor this variable. ,
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' 4.0 PLANT-SPECIFIO POSITION ON EACH VARIABLE 4.2 Brunswick's Position on RC 1.97 Type B Variables 4.2.2 Variable B2 - Control Rod Position Brunswick is in agreement with RG 1.97 and indication is provided to monitor this variable.
4.2.3 Variable B3 - RCS Soluble Boron Concentration Bruns' wick concurs with the ability to obtain a sample o'f reactor core coolant. Sampling will be done through the Post-Accident Sampling System. Analysis will be perf.ormed in accordance with NUREG-0737. Item II.B.3.
4.2.4 v.ariable B4 - Coolant Level in Reactor Refer to variable A2, paragraph 4.1.2.
4.2.5 variable B5 - BWR Core Thermocouples Not required at this time per Supplement 1 to NUREG-0737.
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4.2.6 Variable'B6 - RCS Pressure Refer to variable Al paragraph 4.1.1.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.2 Brunswick's Position on RG 1.97 Type B Variables 4.2.7 variable 57 - Drywell Pressure Refer to variable AS, paragraph 4.1.5.
t 4.2.8 variables B8 - Drywell Sump Level The Brunswick plant design does not require continuous measurement of drywell sump level. A LOCA signal will prevent operation of the sump pumps and will close containment isolation valves to eliminate the possibility.
of radioactive materials leaking outside the primary containment. During and after a LOCA, the drywell sumps overflow to the suppression pool. Measuring sump level after an accident would not accomplish anything.
4.2.9 variable B9 - Primary Containment Pressure Total primary containment pressure is monitored by the combination of drywell pressure and suppression pool pressure. 'Rafer to variable AS, paragraph 4.1.5 and variable A7, paragraph 4.1.7.
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i 4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.2.10 Variable B10 - Primary Containment Isolation Valve Position Brunswick provides position indication for all isolation and containment boundary valves except check valves and manually operated valves.
4.3 Brunswick's Position on RG 1.97 Type C Variables RC 1.97 defines Type C variables as "those variables that provide information to indicate the potential for being breached or the actual breaching of the barriers to fission product releases. The barriers are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment." Key variables under Type C are "those variables which most directly indicate the accomplishment of a safety function." Each variable is . discussed in the following paragraphs and where this variable is covered under another variable type, it is indicated.
4.3.1 C1 - Radioactivity Concentration or Radiation Level in Circulating Primary Coolant Brunswick does not intend to continuously monitor the radioactivity level of the primary coolant. During normal operation the Radiation Monitoring System provides indication of breach. During accident conditions the Post-Accident Sampling System will provide local indication of Rev. 1
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radioactivity concentration in the reactor coolant while samples are being takan for analysis.
4.3.2 variable C2 - Analysis of Primary Coolant Brunswick concurs and will provide a system that meets the requirements of NUREG-0737 Item II.B.3.
4.3.3 Variable C3 - BWR Thermocouple See variable B5, paragraph 4.2.5.
4.3.4 variable C4 - RCS Pressure The requirements for the variable are met by variable A1, paragraph 4.1.1.
4.3.5 Variable C5 - Primary Containment Area Radiation See Variable Ei, paragraph 4.5.1.
4.3.6 Variable C6 - Dryvell Drain Sumps Level See discussion for variable B8, paragraph 4.2.8.
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r 4.3.7 Variable C7 - Suppression Pool Water I.evel Refer to variable A4, paragraph 4.1.4.
4.3.8 variable C8 - Drywell Pressure Refer to variable A5, pabagraph 4.1.5.
4.3.9 _
variable C9 k RCS Pressure (0 to 1500 pain)
Refer to variable A1, paragraoh 4.1.1.
4.3.10 vaciable C10 - Primary Containrsent Pressure
! ReferTto varable A5, paragraph 4.1.5 and variable A7,
. . paragraph 4.1.7.
.< s 4.3.11 variable C11 - Containment & Drywell Hydrogen Concentration
, V Refer to variable A8, paragraph 4.1.8.
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' 4.3.12 variable C12 - Containment & Drywell Oxygen Concentration i .f Refer to variable A8, paragraph 4.1.8.
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4.0 FLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.3.13 variable C13 - Containment Effluent Radioactivity - Noble Cases Refer to variables E4 and E5, paragraph 4.5.4 and 4.5.5.
4.3.14 g lable C14 - Radiation Exposure Rate Not required at this time per Supplement 1 to NUREG-0737.
4.3.15 variable C15 - Effluent Radioactivity - Noble Cases Refer to variables E4 and E5, paragraph 4.5.4.
4.4 Brunswick's Position on RC 1.97 Type D Variables Type D variables as stated in the RG are, "those variables that provide information to indicate the operation of individual safet'.'
systems and other systems important to safety. These variables are to help the operator make appropriate decisions in using the individual systems important to safety in sitigating the consequences
.cf an accident." Key variables that are type D are defined as "those
,.. variables that most directly indicate the operation of a safety system." These variables are discussed in the following paragraphs and where the variable has been covered under another variable type, it is indicated.
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4.0 PLANT-SPECIFIC FOSITION ON EACH VARIABLE (Cont'd) 4.4 ' Brunswick's Position on RG 1.97 Type D Variables 4.4.1 Variable D1 - Main Feedwater Flow Brunswick is in agreement with RC 1.97 concerning this variable. At the Brunswick plant there is a minor range deficiency on the high end of 0.212%. This is a negligible value. The "110% of design value" stated in the RG is considered a guideline. Brunswick will use the current value of 12,000,000 #/hr, for high end monitoring.
4.4.2 Variable D2 - Condensate' Storage Tank Level Brunswick concurs with RG 1.97.
4.4.3 Variable D3 - Suppression Spray Flow Brunswick does not concur with RC 1.97 on this variable.
For the Brunswick design RHR flow can be used to monitor che operation of. primary containment related systems.
Also, the following parameters give indication that the safety system is accomplishing its task Rev. 1
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f 4.0 PLANT-SPECIFIC POSITION ON EACM VARIABLE (Cont'd) 4.4.3 (Continued)
Drywell Pressure - A5, B7, C8, D4, 39, C10 Drywell Temperature - A6, D7 Suppressic,n Pool Press are - A7 Suppression Pool. Temperature - A3, D6.
RRR flow and the above list of variables provide adequate information to monitor operation of primary containment related systems.
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4.*4.4 Variable D4 - Dryvs11 Pressure -
Brunswick concurs with RG 1.97 on this variable.
4.4.5 variable D5 - Suppression Pool Water Level Refer to variable A4, paragraph 4.1.4.
4.4.6 variable D6 - Suppression Pool Water Temperature Refer to variable A3, paragraph 4.1.3.
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4.4.7 Variable D7 - Drywell Atmosphere Temperature Refer to variable A6, paragraph 4.1.6.
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440 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on RC 1.97 Type D Variables (Cont'd) 4.4.8 Variable D8 - Drywell Spray Flow Brunswick's position on this variable is the same as that discussed under D3, paragraph 4.4.3.
4.4.9 Variables D9 - MSIV Leakage Control System Pressure These systems are not included in the Brunswick plant design. Brunswick does not intend to add these systems.
4.4.10 Variable D10 - Primary System Safety Relief Valve Positions Including ADS or Flow Through or Pressure in Valve Lines Brunswick is in agreement with RC 1.97 on this variable, and provides instrumentation for this variable.
D11 - Isclation Condenser System Shell-Side Water Level D12 - Isolation Condenser System Valve Position These systems are not included in the Brunswick plant design. Beunswick does noe. intend to add these systems.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on RG 1.97 Type D Variables (Cont'd) 4.4.11 Variable D13 - RCIC Flow BrunJwick agrees with the intent of RG 1.97 concerning this variable. Current design has indication as part of the flow controller and therefore indication is not isolated from the control loop. Brunswick does not plan to provide isolation between indication and control. If controller and/or flow indicator fail, RCIC performance can be monitored by monitoring the response of the reactor water level.
4.4.12 Variables - D14 - HPCI Flow ,
D15 - Core Spray System Flow D16 - LPCI System Flow The HPCI and C3 systems each have one branch line - - the test line - - downstream of the flow - measuring element.
The test line is provided with a mot.or operated valve that is normally closed (two valves in series in the case of the HPCI). Further, t.he valve in the test line closes automatically when the emergency system is activiated, thereby ensuring that indicated flow is not being diverted by the test line. Proper valve position can be verified by a direct indication of valve position. (Although LPCI has Rev. 1
4.0 PLANT-SPECIPIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on EG 1.97 Type D Variables (Cont'd) 4.4.12 (Continued) several branch line's located downstress of each flow measuring element, each of those lines is normally closed.) For all of these systems, there are valid primary indicators other than flow measurement to verify the performance of the emergency system; fo;; example, vessel water level.
The existing flosemeasurement schemes for the HPCI, CS and LPCI are all adequate in that they meet the intent of RG 1.97.
4.4.13 Variable D17 - SLCS Plow The SLC syster is manually initiated. Flow measuring devices were not provided for this system. The pump discharge header pressure, which is indicated in the '
control room, will indicate SLC pump operation. Besides the discharge header pressure observation, the operator can
, verify the proper functioning of the SLCS by monitoring the following:
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- 4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on RG 1.97 Type D Variables (Cont'd) 4.4.13 Variable D17 - SLCS Flow (Cont'd)
- 1. Decrease in the level of the boric acid storage tank.
- 2. Reactivity change in the reactor as measured by neutron flux.
- 3. Squib valve continuity indicating lights.
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The use of these indications is believed to be a valid alternative to SLCS flow indication.
4.4.14 Variable D18 - SLCS Storage Tank Level Brunswick is in agreement with the regulatory guide range of bottom to top level monitoring. At the Brunswick Plant, this level is given in percent.
Brunswick is in disagreement with the category 2 designation for this variable. The current design basis for the SLCS assumes a need for an alternative method of reactivity control without a concurrent loss-of-coolant 4
accicant or high-energy line break. The environment in which the SLCS instrumentation must work is therefore a
" mild" environment for qualification purposes.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on RG 1.97 Type D Variables (Cont'd) 4.4.14 Variable D18 - SLCS Storage Tank Larel (Cont'd)
The current design basis for the SLCS recognizes the system has an importance to safety less than the importance to safety of the reactor protection system and agrees with the graded approach to quality assurance specified in PG 1.97. It is unnecessary to apply a full quality assurance program to this instrumentation. Brunswick will classify this variable category 3. A category 3 requirement is consistent with the 79-018 stand on the SLCSi which is,that the system is 'not required to help mitigate a HELB or a LOCA.
4.4.15 variable D19 - RHR System Flow Brunswick concurs with RG 1.97 on this variable.
4.4.16 Variable D20 - RRR Heat Exchanger Outlet Temperature Brunswick concurs with RG 1.97 on this variable.
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on EC 1.97 Type D Variables (Cont'd)
'4.4.17 variable D21 - Coolina kater Temperature to ESF Components At Brunswick the Service Water System provides cooling water to the ESF components. Water is taken from the Cape Fear River via the intake canal. It is a once-through, open-loop system designed for 338 to 90 F 0 water tesperature according to Brunswick's FSAR. Since there are no heat sources between the intake canal and the ESF components, there will be no significant change in water temperature.
Also, there are no operator actions based on water temperature. The E(F's assume a worst-case water temperature and use this in the calculations. Due to this design there is no need for this indication for post-accident monitoring. There are other indications such as cooling veter flow that can be used to unicor system operation. Brunswick does not intend to provide this variable.
4.4.18 Variable D22 - Coolina Water Flow to ESF System Components Brunswick concurs with RG 1.97 on this variable and will provide flow measurement and indication of main service water flow in the conventional and nuclear service water headers.
Rev. 1
,_. .m.. . _ . . .. . . ..... . .
4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.4 Brunswick's Position on RG 1.97 Type D Variables (Cont'd) 4.4.19 _ Variable D23 - 31gh Radioactivity Liquid Tank Level i
Brunswick concurs with RG 1.97 on this variable.
4.4.20 Variable D24 - Emergency Ventilation Damper Position Brunswick concurs with RG 1.97 on this variable. Brunswick interprets this variable to be dampers which could release radiation to the surrounding plant environment or expose control room personnel to radiation.
4.4.21 Variable D25 - Status of Standby Power & Other Energy Sources Important to Safety (Electric. Hydraulic, Pneumatic)
At Brunswick the standby AC power supply and distribution system for the two units consists of four diesel generators and four 4.16 kv Class IE buses. The 4 kv emergency buses are El, E2, E3 and E4. The voltage is stepped down to the 480V emergency buses ES, E6, E7, and E8. The 480V emergency bus feeds the 120V AC emergency bus.
Rev. 1
I i
4.0 PLANT-SPECIFIC POSITI0t! ON EACH VARIABI.E (Cont'd) 4.4 Brunswick's Position on RG 1.97 Type D Variabler, (Cont'd)
The DC standby power is supplied by batteries. The instrument air pressure is supplied by the standby air compressors.
Diesel generator terminal voltage, feeder breaker indication, and feeder breaker trip annunciation are provided in the control room and provide adequate information on bus voltage. Also, process computer points E039, E040 and E042 give Els E2, E3, and E4 feeder bus voltage respectively.
Feeder breaker trip annunciation is available in the control room for both the 480V s-d the 120V AC emergency buses. Feeder breaker indication and feeder equipment malfunction annunciation are available for the 480V emergency bus.
Brunswick believes that its treatment of this variable is adequate in that it provides information which is consistent with the definition of the Type D variable.
Rev. 1 l'
r 4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE, (Cont'd) 4.4 Brunswick's Position on RC 1.97 Type D Variables (Cont'd) 4.4.22 Plant Designer Selected Variables In accordance with RC 1.97's statement, "The plant designer should select variables and information display channels required by his design to enable the control room personnel to ascertain the operating status of each individual safety system and other systems important to safety to the extent necessary to determine if each system is operating or can be placed in operation...", Brunswick has sele'eted four additional type D, category 3 variables to monitor. The basis for choosing these variables is the capability of using the main condenser as a heat sink for main steam from the reactor. This involves bypassing the main turbine provided the hotwell level is low enough to accommodate additional condensate, and that there is suffJcient vacuum for operation. Verification of the number of condensate pumps running is also recommended. The four variables are:
D26 - Turbine Bypass Valve Position D27 - Condenser Hotwell Level D28 - Condenser vacuum D29 - Condensate Pump & Booster Pump Status i
Rev. 1 C- ~
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.5 Brunswick's Position on RG 1.97 Type E Variables The RG 1.97 definition for type E variables is: "those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and for continually assessing such releases." Key variables that are type E are defined as variables thu most directly indicate the relemoe of radioactive material.
Each variable is discussed in the following paragrsphs and Brunswick's posief.on on the variable is given. Where a variable has already been discussed under another type, it is indiented.
4.5.1 Variable Ei - Primary Containment Area Radiation - High Range Brunswick concurs with the RG 1.97 recommendation on this variable and the requirements of NUREC 0737 (Table II.F.1-t 3). Brunswick is currently installing equips,ent to measure f
this variable. Refer to TMI plant modifications80-030 and 80-031.
4.5.2 Variable E2 - Reactor Building or Secondary Containment Area Radiation
~ See Variable C14, paragraph 4.3.14.
Rev. 1
____ ,_ m , . _ . _ ___ . - _ . ,_ . _ _ _ . , . _ _ . , ._ . .
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4.0 PLANT-SPECIPIC POSITION ON EACH VARIABLE (Cont'd) 4.5 Brunswick's Position on RG 1.97 Type E Variables (Cont'd) 4.5.3 Variable E3 - Radiation Exposure Rate The stated purpose of this variable is to monitor buildings or areas where access is required te service safety equipment. The Brunswick plant is not designed for servicing equipment in the reactor building during or af ter an accident. Redundancy of system design sitigates the requirement for servicing a safety system after an accident.
4.5.3 Variables E4 - Noble Gases and Vent Flow Rate ES - Particulates and Halogens In the Brunswick design there are five identifiable release points: the stack, two turbine building vents, and two reactor building vents. The instrumentation on the reactor building vents is not required because the reactor building isolates upon the receipt of a high radiation signal to the monitoring instrumentation. CP&L has NRC approved for this position provided in a letter from _the NRC dated May 5, I?S2, concerning NUREG-0737 Action Items II.F.1.1 (Noble Gas Monitor) and II.F.1.2 (Iodine / Particulate Sampling).
Rev. I n.,--=.-.- -._._.__._._.=_.__._._._._---._-.....--_--..
4.0 PLANT-SPECIFIC POSITION ON EACH VARIABLE (Cont'd) 4.5 Brunswick's Position on EG 1.97 Type E Variables 4.5.4 (Continued)
L Under variable E4 in RG 1.97,'there are six tab-headings.
For convenience and clarity of discussion, the six are listed below and their applicability to Brunswick summarised:
RG 1.97- Brunswick
- 1. Drywell Purge, SGTS Stack
, 2. Secondary Containment Purge Reactor Building
- 3. Secondary Containment (RX Shield Bldg. Annulus) N/A
- 4. Auxiliary Building N/A
- 5. Common Plant Vent Stack
- 6. All other Release Points Turbine Vents Instrumentation for the stack and turbine building vents will be provided through TMI plart modificationa 80-034, 35 and 36. These plant modifications meet the requirements of NUREG-0737 and applicable standards end regulatory guides incisding RC 1.97.
Rev. 1
l
. 4.0 PLANT-SPECIFIC POSITION ON.EACH VARIABLE (Cont'd)
( 4.5 Brunswick's Position on RG 1.97 Type E Variables (Cont'd) 4.5.5 variable E6 - Radiation Exposure Meters On hold due to lack of requirements from NRC. Refer to NRC ERRATA dated July 1981.
4.5.6 variable E7 - Airborns Radiohalogens and Particulates Portable Sampling with On-Site Analysis Capability)
Brunswick concurs with RG 1.97.
4.5.7 variable E8 - Plant & Environs Radiation (Portable Instru-mentation)
Brunswick concurs with RG 1.97.
4.5.8 variable E9 - Plant & Environs Radioactivity (Portable Instrumentation)
Brucswick concurs with RG 1.97.
4.5.9 Variables E10 - Wind Direction E11 - Wind Speed E12 - Estimation of Atmosphere Stability Brunswick will install new equipment which will meet the recommendations of RG 1.97.
Rev. 1
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4.0 PLANT-SPECIFIC POSITION ON EACH VARIABI.E (Cont'd) 4.5 Brunswick's Position on EG 1.97 Type E Variables 4.5.10 variable E13 - Primary Coolant & Sump Accident SamplinS of primary coolant will be done at two points in the jet pump pressure instrument system and from a single sample line connected to both loops in the RER system. Refer to Plant Modification 80-28 and 80-29.
Sampling of the containment sumps is not necessary at the Brunswick plant because acciden.t conditions will close isolation valves G16-F003, P004, F019 and F020, which a
prevents release of radioactive materials from primary containment. .
4.5.11 Variable E14 - Containment Air Containment air sampling will be taken from the dryvell and suppression pool atmosphere. Refer to Plant Modification 80-028 and 80-029. .
Rev. 1
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. 5.0 ABBREVIATIONS ADS - Automat.ic Depressurization Systen BWR - Boiling Water Reactor Br.10G - Boiling Water Reactor Owners Group CAD - Containmer.t Atmospheric Dilution ,
1 CS - Core Spray ECCS -
Emergency Core Cooling System ESF -
Engineered Safety Features FSAR -
Finimi Safety Analysis Report HPCI - High Pressure Coolant Injection LPCI - Low Pressure Coolant Injection NA -
Not Applicable QA --
Quality Assurance KCS -
Reactivity Control System l
RCIC ,- Reactor Core Isolation Cooling RG -
Regulatory Guide RIR -
Residual Heat Renoval RPV -
Reactor Pressure vessel RWCU -
Reactor Water Clean Up R1 - Reactor R/hr - Rams per hour SGTS - Standby Gas Treatment System SLCS -
Standby Liquid Control System SRV - Safety Relief Valve TMI -
Three Mile Island Rav. 1
l
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6.0 REFERENCES
- 1. ANS 4.5
- 2. Brunswick PSAR
- 3. Brunswick System Descriptions
- 4. BWROC Emergency Procedure Guidelines, Rev. 3 (Prepublication draf t)
- 6. IE Bulletin 79-01B
- 7. NUREG-0578
-8. NUREG-0737 and Supplement 1
- 9. Plant Hodifications:
77-268, Pressure Switch Analog Replacement UI 77-269, Pressure Switch Analog Replacement U2 77-303, CST & MVD Level Indicator Addition fs Range Change 80-137, TSC Computer Input Points U1 80-138, TSC Computer Input Points U2 80-180, Nuclear Boiler Instrumentation U1 80-181, Nuclear Boiler Instrumentation U2 81-251, Suppression Pool Instrumentation U1 81-252, Suppression Pool Instrumentation U2 82-049, Dryusil RTD Replacement
- 10. RC 1.97, Rev. 2, Rev. 'l
- 11. TMI Action Item Plant Modifications:
80-025, Drywell Pressure Instrumentation U1 80-026, Drywell Pressure Instrusentation U2
~
80-028, Improved Post Accident Sampling UI Rev. 1
k
6.0 REFERENCES
(Cont'd) .
- 11. (Continued)80-029, Improved Post Accident Sampling U2 80-030, containment Bad Monitoring U1 80-031, Containment Rad Monitoring U2 80-032, Containment Hydrogen Monitoring U1 80-033, Containment Hydrogen Monitoring U2 80-034 TB Vent High Range Rad Monitor U1 80-035, TB Vent High Range Bad Monitor U2 80-036, Stack Radiation Monitors80-378, Wide Range Torus Level U1 80-079, Wide Range Torus Level U2 .
- 12. 10CFR50 Appendix A and General Design Criteria 13,19, and 64
- 14. NEDC-22253, BWR Owners' Group Evaluation of Containment Isolation Concerns P.sv. 1 i i -_-_.w__n_i_____m._t-.1._n_.___s___. _t___ _.--____._______11__
2.____._ 1 ____.m. _ _ . _ _ _ _ _______________m * -
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e e.a l
CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT BRUNSWICK RESPONSE TO NUREG 737 SUPPLEMENT 1 -
REGULATORY CUIDE 1.97 - APPLICATION TO EMERGENCY RESPONSE FACILITIES DATE: f/ 7 SUBMITTED BY: h[ h MM Mde ,[ ,
RECOMMENDED BY: M - -
APPROVED BY:
7 7 REV. NO. SUBMITTED BY RECOMMENDED BY APPROVED BY DATE 1 hd & ]$ ))h //jk y , -
l r_m -__rrr -_ur r - -, - - - - - - ~
- - - --- )
TABLE OF CONTENTS Title M GENERAL NOTES iii VARIABLE A1 - RPV PRESSURE 1 VARIABLE A2 -
RPV WATER LEVEL 2 VARIABLE A3 -
SUPPRESSION POOL WATER TEMPERATURE 4 VARIABLE A4 -
SUPPRESSION POOL WATER LEVEL 5 VARIABLE A5 -
DRYWELL PRESSI'RE 6 VARIABLE A6 -
DRYWELLL TEMPERATURE 7
-VARIABLE A7 -
SUPPRESSION POOL "".::SSURE 8 VARIABLE A8 -
DRYWELL AND SUPPRESSION POOL HYDROCEN AND OEYGEN CONCENTRATION 9 VARIABLE B1 -
NEUTRON FLUE 10 VARIABLE B2 - CONTROL ROD POSITION 11 VARIABLE B3 -
RCS SOLUBLE BORON CONCENTRATION 12 VARIABLE B4 -
COOLANT LEVEL IN REACTOR 13 VARIABLE B5 -
BWR CORE TEMPERATURE 13 VARIABLE B6 - RCS PRESSURE 13 VARIA3LE B7 -
DRYWELL PRESSURE 13 VARIABLE 58 -
DRYWELL SUMP LEVEL 13 VARIABLE B9 -
PRIMARY CONTAINMENT PRESSURE 13 VARIABLE B10 -
PRIMARY CONTAINMENT ISOLATION 14 VALVE POSITION VARIABLE C1 -
RADIOACTIVITY CONCENTRATION OR RADIATION LEVEL IN CIRCULATING PRIMAR't COOLANT 22 VARIABLE C2 -
ANALYSIS OF PRIMARY COOLANT (CAMMA SPECTRUM) 23 VARIABLE C3 -
BWR CORE TEMPERATURE 24 VARIABLE C4 -
RCS PRESSURE , 24 VARIABLE C5 -
PRIMARY CONTAINMENT AREA RADIATION 24 VARIABLE C6 -
DRYWELL DRAINS SUMP LEVEL 24 VARIABLE C7 -
SUPPRESSION POOL WATER LEVEL 24 VARIABLE C8 -
DRYWELL PRESSURE 24 VARIABLE C9 -
RCS PRESSURE 24 VARIABLE C10 -
PRIMARY CONTAINMENT PRESSURE 24 VARIABLE C11 -
CONTAINMENT AND DRYWELL HYDROGEN CONCENTRATION 24 VARIABLE C12 -
CONTAINMENT AND DRYWELL OXYGEN CONCENTRATION 24 VARIABLE C13 -
CONTAINMENT EFFLUENT RADI0 ACTIVITY-NOBLE CASES 24 VARIABLE C14 -
RADIATION EXPOSURE RATE 24 VARIABLE C15 -
EFFLUENT RADIOACTIVITY 24 LRIABLE D1 -
MAIN PEEDWATER PLOW 25 VARIABLE D2 -
CONDENSATE STORAGE TAlet LEVEL 26 VARIABLE D3 -
SUPPRESSION SPRAY FLOW 27 VARIABLE D4 - DRYWELL PRESSURE 28 VARIABLE D5 -
SUPPRESSION POOL WATER LEVEL 29 VARIABLE D6 .- SUPPRESSION POOL WATER TEMPERATURE 29 VARIABLE D7 -
DRYWELL ATMOSPHERE TEMPERATURE 29 i Rev. I
~ . - - - _ - _ - _ . _ _ _ _ - _ _ = _ _ - ___- =_ _ ._
f f
Table of Contents (Cont'd)
VARIABLE D8 -
DRYWELL SPRAY FLC1 29 VARIABLE D9 -
MSIV LEAEAGE CONTROL SYSTEM PRESSURE 29 VARIABLE D10 -
PRIMARY SAFETY RELIEF VALVE POSITION 30 VARIABLE D11 - ISOLATION CONDENSER SYSTEM SHELL-SIDE WATER LEVEL 32 VARIABLE D12 - ISOLATION CONDENSER SYSTEM VALVE POSITION 32 VARIABLE D13 -
RCIC FLOW CONTROL 33 VARIABLE D14 -
HPCI FLOW 34 VARIABLE D15 -
CORE
- SPRAY SYSTEM l' LOW 35 VARIABLE D16 - LPCI SYS*EM FLOW 36 VARIABLE D17 - SLCS FLOW 36 VARIABLE D18 -
SLCS STORACE TANK LEVEL 37 VARIABLE D19 - RER SYSTEM FLOW 38 VARIABLE D20 - RHR HEAT EXCHANGER OUTLET TEMPERATURE 39 VARIABLE D21 - COOLING WATER TEMPERATURE TO ESF SYSTEM -
COMPONENTS 40 VARIABLE D22 -
COOLING WATER FLOW TO ESF COMPONENTS 41 VARIABLE D23 -
HIGH RADIOACTIVITY LIQUID TAIEC LEVEL 43 VARIABLE D24 -
EMERGENCY VENTILATION DAMPER POSITION 44 VARIABLE D25 - STATUS OF STANDBY POWER AND OTHER ENERGY SOURCES IMPORTANT TO SAFETY (ELECTRIC HYDRAULIC. PNEUMATIC) 48 VARIABLE D26 - TURBINE BYPASS VALVE POSITION 52 VARIABLE D27 -
CONDENSER HOTWELL LEVEL 53 -
VARIABLE D28 -
CONDENSER VACUUM. 54-VARIABLE D29' - CONDENSATE PUMP AND BOOSTER PUMP STATUS 55
~ VARIABLE E1 -
PRIMARY CONTAINMENT AREA RADIATION-HIGH RANCE 57 VARIABLE E2 -
REACTOR BUILDING OR SECONDARY CONTAINMENT AREA RADIATION 59 VARIABLE E3 - ' RADIATION EXPOSURE RATE 60 VARIABLE E4 -. NOBLE GASES AND VENT FLOW RATE 61 VARIABLE E5 -
PARTICULATE AND HALOGEN 61 VARIABLE E6 ~~ RADIATION EXPOSURE METERS 64 VARIABLE E7 -
AIRBORNE RADIOHALOCENS AND PARTICULATES 65 VARIABLE E8 -
PLANT AND ENVIRONS RADIATION 66
. VARIABLE E9 - PLANT AND ENVIRONS RADIOACTIVITY 67 VARIABLE E10 - WIND DIRECTION 68 VARIABLE E11 -
WIND SPEED 68 VARIABLE E12 -
ESTIMATION OF ATMOSPRERIC STABILITY 68 VARIABLE E13 - PRIMARY COOLANT AND SUMP 70 VARIABLE E14 -
CONTAINMENT AIR- 72 11 Rev. 1 E _ ___ _ . - - - - - - - - - - - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - - _ _ _
CENERAL NOTES Use of Table Bach variable contains the eight items, lettered (a) through (h), requested in Supplement 1 to NUREG-0737 on page 14. To the right of each item are two columns. The first coluna gives Regulatory Guide 1.97 recommendations and the
-other indicates what is currently provided at Brunswick.
Item (h) describes what action, if any, is tc be taken toward the variable.
The designation of 1E appearing under item (e) states that the power supply is fed from standby power.
This report is applicable to Unit 1 and Unit 2. Where differences exist, they are so noted. .
Specific Notes (References by specific Variable)
NOTE 1: All. essential transmitters are being qualified by 79-015.
Indicators and recorders located in the Control Room shall not be environmentally qualified by testing. Justification for this approach is given in the Brunswick position on RG 1.97, paragraph 1.3.1.a.
NOTE 2: ' See Brunswick positf on on RG 1.97, paragraph 1.3.1.e.
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l l iii Rev. 1
i LIST OF EFFECTIVE PAGES I
Brunswick Response to NUREG 737 Supplement 1 - Regulatory Guide 1.97 - Application to Emergency Response Facilities Page(s) Revision 0
0 1-iv 1 1-73 1 S
iv Rev.1
VARIABLE Al - RPV PRESSURE Recommended Provided by Brunswick by RC 1.97 (a) Instrument Range 0-1500 psig 0-1200 psig (b) Environmental Qualification Yes Note 1 (c) Seismic Qualification Yes Note 1 (d) Quality Assurance Yes Note 2 l (e) Power Supply 1E 1E (f) Redundance and Sensor Imcation Yes Yes l': Tag No. Range Location Sensor Transmitter C32-PT-N005A 0-1200 psig Il21-P004 - Reactor Building Transmitter C32-PT-N005B 0-1200 psig Il21-P005 - Reactor Luilding (g) Location of Display Display Tag No. Range Location Indicator C32-P1-R605 0-1200 psig til2-P603 - Control Room Indicator C32-PR-R608 . 0-1200 psig H12-P603 - Control Room (h) Schedule - System will be modified to provide the required range. Work f or Unit I will be scheduled for completion during refueling outage #5 and work for Unit 2 will be scheduled for completion during refueling f6.
1 Rev. 1
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VARIABLE A2 - RPV WATER LEVEL Recommended By RCl.97- Provided by Brunswick (a) Instrument Range -180 to + 295" -100 to +550" ,
(b) Environmental Qualification Yes Note 1 (c) Seismic Qualification Yes Note 1 (d) Quality Assurance Yes Note 2 )
l (e) Power Supply lE lE l (f) Redundance and Sensor Location Yes Partial Redundancy Sensor Tag. No. Range Location Transmitter B21-LT-NO36 -100 to + 200" H21-P009 - Reactor Building Transmitter B21-LT-NO37 -100 to + 200" H21-P010 - Reactor Building Transmitter B21-LT-N026A 0 to 210" H21-P004 A - Reactor Building Transmitter B21-LT-N026B 0 to 210" H21-P005B - Reactor Building Transmitter B21-LT-N027 +150 to + 550" H21-P004B - Reactor Building 2 Rev. 1
- 1. p
._ a s
',.' , L 'g ]
- VARIABLEA2-RP(WATERLEVEL(Con?j]},
i
) -(g) Location of Display..
I Display . Ts@2 Range Location i Indicator B21-LI-R610 "1., -100 to'+ 200" H12-P601 - Control Room
. Recorder .B21-LR-R$15 - -300 to + 200" H12-P601 - Control Room .
Indicator B21-LI-R604A "O to 210" H12-P603 - Control Room Indicator B21-LI-R604B O to 210" H12-P603 - Control Room Indicator B.21-LI-R605- +150 to + 550" H12-P603 - Control Room j
- Indicator. 'C32-LI-R606A ' +150 to + 210" H12-P603.- Control Room
- Indicator .C32-LI-R606B +150 to + 210" H12-P603 - Control Roon 5
- Indicator C32-LI-R606C +150 to + 210" H12-P603 - Control Room
- Will not be used for post accident monitoring. s j (h) Schedule - Transmitters B21-LT-NO36, NO37 will be respanned to satisfy the low range requirement.
}
A _ transmitter and indicator will be added to sdtisfy redundancy for th high level range.
p i A redundant power supply will be added for B21-LT-N026B. Work for Unit 1 will be scheduled for completion l.!
during refueling outage #5 and work for Unit 2 will be scheduled for completion during refueling outage i #6, Transmitter B21-LT-N027 will be replaced to comply with environmental qualification on a schedule l consistent with IE Bulletin 79-01B and 10CFR50.49. l l
t 3 Rev. I r
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e 4
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5 E
5 5 VARIABLE A3 - SUPPRESSION POOL WATER TEMPERATURE Recommended E by RG 1.97 Provided by Brunswick E
(a) Instrument Range 30-230 F 0-400 F Yes Note 1 F (b) Environmental Qualification Yes Note 1 .
(c) Seismic Qualification
> Note 2 Yes
- (d) Quality Assurance lE 1E h (e) Power Supply Yes Partial - Div. I and Div. II N (f) Redundance and Sensor Location sensors, but only one recorder, g
Tag No. Range Location f Sensor RTD CAC-TE-1258-14 0-400 F Suppression Pool RTD CAC-TE-1258-21 0-400 F Suppression Pool e
E (g) Location of Display ,
Display Tag No. Range Location Recorder CAC-TR-1258 0-400 F XU Control Room 5 (h) Schedule - Plant Modifications81-251 and 81-252 will upgrade the existing temperature E monitoring system to meet NUREC 0661 requireraents and RG 1.97 recommendations.
Unit 1 work will be scheduled for completion during ref.ueling outage #4 and Unit 2 l-
- work will be scheduled for completion during refueling outage #5.
/
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Rev. I 2
fi 4
5 5-E-
K
+
VARIABLE A4 - SUPPRESSION POOL WATER LEVEL Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range -10' to +6' -10' to +6 '
Yes Yes )
'(b) Environmental Qualification -l
]
Yes Yes l
. (c)' Seismic Qualiffemtion ,
l Yes Yes (d) Quality Assurance i
IE 1E (e) Power Supply Yes Yes (f) Redundance & Sensor Location Tag Number Range Location Sensor-
-10' to +6' Reactor Building Transmitter CAC-LT-2601
[
Transmitter CAC-LT-2602 -10' to +6' Reactor Building l .+10' to +6' Reactor Building Transmitter CAC-LT-3342
-42" to -18" Reactor Building Transmitter CAC-LT-4177
} (g) Location of Display Range Location Display . Tag Number CAC-LI-2601 -10' to +6' XU-51, Control Room Indicator XU-51, Control Room Recorder CAC-LR-2602 -10' to +6' CAC-LI-3342 -10' to +6' IR-RB-4
' Indicator XU-51, Control Room Indicator CAC-LI-4177 -42" to -18" l}
l (h) Schedule: No changes are anticipated to this instrumentation.
O t
5 Rev. 1
f-VARIABLE A5 - DRYWELL PRESSURE-Recommended RC 1.97 Provided by Brunswick (a) -Instrument Range -5 to +245 psig -5 to +245 psig (b) Environmental Qualification Yes Note 1 (c) Seismic Qualification Yes Note 1 (d) Quality'Assutance .Yes Note 2 (e) .1'ower Supply lE 1E (f) Redundance.& Sensor Location Yes Yes i
I Sensor Tag Number Range Location I Transmitter CAC-PT-4175 -5 to +245 psig Reactor Building CAC-PT-4176
-5 to +245 psig Reactor Building Transmitter 1
f (g) Location of Display
\
\
Tag Number Range location i Display Recorder CAC-PR-1257-1 -5 to +245 psig XU Control Room Indicator CAC-PI-4176 - -5 to +245 psig XU Control Room (h) Schedule - No changes to existing instrumentation are anticipated.
6 Rev. 1 9
+
VARIABLE A6 - DRYWET.L TEMPERATURE
,- i Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range 40 to 440 F 0 to 400 F f (b) Environmental Qualification Yes Note 1 (c) Seismic Qualification Yes Note 1 l
l (d) Quality Assurance Yes Note 2 l h 1 1
(e) Power Supply lE lE
'l (f) Redundance & Sensor Location Yes Partial - Div. I and Div. II l
Sensors, but only one Recorder Sensor Tag Number Range Location 1
Temperature Element CAC-TE-1258-1,2,3,4,5,6, 7,8,9,10,11,12,13,22,23,24 0 to 400 F Drywell (g) Location of Display ,
Display Tag Number Range Location
)
Recarder CAC-TR-1258 0 to 400 F XU-3 Control Room (h) Schedule - The existing system will be modified to provide redundant recordin g,* l and range.
Unit I work will be scheduled for completion during refueling outage #5 and Unit 2 work will be scheduled for completion during refueling outage #6.
- Redundan~cy is provided for this variable in that there are at least two sensors at each elevation zone in the drywell. These sensors are not necessarily at the same azimuth.
Rev. 1 7
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I i
VARIABLE A7 - SUPPRESSION POOL PRESSU?.E
, Required by
'- RC 1.97 Provided by Brunswick
(-
(a) -Instrument Range -5 to 186 psig 0-75 psig f
t I (b)- Environmental Qualification Yes Note 1
, (q)- Seismic Qualification Yes Note 1
,i j (d)' Quality Assurance Yes Note 2 l l
1 j (e) Power Supply 1E 1E j i Yes No T (f) Redundance and Sensor. Location Sensor Tag Number Range Location li CAC-PT-1257-2 0-75 psig Reactor Building Transmitter,
'(g) Location of Display .
Display Tag Number' Range Location Indicator CAC-PI-1257-3 0-75 psig XU Control Room
] (h) Schedule 3
1 A redundant transmitter and indicator will be installed. The range will be changed to 1 -5 to +245 psig. Unit I work will be echeduled for completion during refueling outage #5
' and work for Unit 2 will be scheduled for completion during refueling outage #6.
8 Rev. 1 1
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e e
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! VARIABLE A8 - DRYWELL AND SUPPRESSION POOL HYDROCEN & OXYCEN CO!! CENTRATION Recommended by Provided by Brunswick RC 1.97 (a) Instrument Range .
l' Hydrogen, 0-30% 0-5%, 0-25%) Does not meet 12 psia 0xygen 0-10% 0-10%, 0-20%) to design pressure
]i recommendation of RC'1.97~
(b) Environmental Qualification .Yes Note 1 S
l' (c) Seismic Qualification Yes Note 1 (d) Qiality Assurance Yes Note 2 (e) Power Supply 1E. lE (f) Redundance and Sensor Location Yes Yes Sensor Tag Number Range Location Monitor CAC-AT-1259 See above Reactor Building
)l Monitor CAC-AT-1263 See above Reactor Building b
f; '(g) Location of Display -
a Display, Tag Number Range Location ll 4
i Recorder CAC-AR-1259 See above XU Control Room l Recorder CAC-AR-1263 ,
See above XU Control Room (h) Schedule - The current system will be upgraded to improve reliability. The range and design l pressure recommendations of RG 1.97 will be met. Unit 1 is being installed on the current
? outage. Unit 2 will be upgraded on the next scheduled outage of sufficiet t duration to accomplish
[ the remaining work.
4 9 Rev. 1
VARIABLR B1 - NRUTRON FLUX .
. Recommended By RC 1.97 Provided by Brunswick "i
(a) Instrument Range 10~0%'to 100% 107 % > Range > 100% Full Power Full Power i
(b) Environmental Yes Note 1 Qualification (c) ' Seismic Yes Note 1 l:
1 Qualification ,
(d) Quality- Yes Note 2 Assurance ii (e) Redundance Yes. Yes"- Sensors are located in reactor core lI & Sensor Location s ll (f) Power Supply 1E 1E (g) Location of
, Display l.
Display Range Location
! 3 No.
~1 0 N12-P603 Control Room T Indicator C51-NI-R600A 10
~I to 10 counts /sec " " "
l Indicator C51-NI-R600B 10
-t to 106 e unts/sec " " "
Indicator C51-NI-R600C 10-g to 10 * **"
.; Indicator C51-ill-R600A 10 to 10 6 coun
- ""ts/sec " " "
o Indicator C51-NI-R601A -100 to =* to +10 period in sec " "
Indicator C51-NI-R601B " " " "
Indicator C51-NI-R601C " " "
Recorder C51-NI-R602 0-40%, 0-125% Full Power " "
Recorder C51-NI-R603A " " "
Recorder . C51-HI-R603B " " " "
Recorder C51-NI-R603C " " " "
Recorder C51-HI-R603D " " "
1- Indicator C51-NI-R604(X)* 0-125% Full Power l
- There are 16 LPRM's (h) Schedule - There are no anticipated changes to this system.
10 Rev. 1
.u
. e.
.l VARIABLE B2 - CONTROL ROD POSITION
' Recommended by RC 1.97 Provided by Brunswick
- (a) Instrument Range Full'In Full in - Full out.
i Full Out i
l Note 1 j (b) Environmental No i Qualification (c) Seismic Qualification No Note 1
! (d) Quality Assurance High Quality Commercial , Note 2 I Crade (e) Power Supply Non-1E High Reliability (f) Redundance and .No No P Sensor Location Sensor Tag Number Range Location Position Switch C12-35-XX-XX* Full in-Full out Control Rod
(
j (g) . Location of Display 1
j Display Tag Number Range Location
! H12-P603 Control Room Indicator C12 Full-In-Full-Out (h) Schedule: There are no anticipated changes to the RPIS (Rod Position Indication System).
- NOTE: There are 137 Control Rod Drive Position Indicator Probes.
11 Rev. 1
{
4 Recommended By RG 1.97 Provided by Brunswick' k
(a) Instrument Range 0-1000 ppa. Range exceeds RC 1.97 Recommendation 4 (b) Environmental Qualification No specific position Sampling System will'be qualified. Analysis equip -
ment is high quality commercial.
lf p .
(c) Seismic Qualification. No specific. position Sampling system t ill be seismically qualified Analysin i' equipment has not been qualified.
(d) Quality Assurance High Quality Sampling System has full QA Program commitment.
Commercial Grade Analysis equipment is high quality commercial grade.
(e) Power Supply Non-lE lE i (f) Redundance & Sensor No . Redundant Sample Points Only Location g
RCS Samples are taken from the RHR Heat Exchanger A and B shell sides'and from the No. 6 and No. 14 jet pumps. .
$ (g) Location of Display j The sample will be analyzed on site in the chemistry lab located in the service building. Back up j analysis will be performed by Babcock and Wilcox. Boron concentration is logged by the laboratory technician and phoned in to t,he .ontrol room operator where it is logged by him.
(h) Schedule 1
THI modifications80-028 and 80-029 have provided this Post Acc.ident Sampling Systec.
i 12 Rev. 1
~
P VARIABLE B4 - COOLANT LEVEL IN REACTOR - RC 1.97 recommendations will be met by Variable A2.
L r
VARIABLE B5 - BWR CORE TEMPERATURE - Not required at this time per NUREG-0737 supplement 1.
VARIABLE B6 - RCS PRESSURE - RG 1.97 recommendations will be met by Variable A1.
L VARIABLE B7 - DRYWELL PRESSURE - RG 1.97 recossmendations will be met by Variable AS.
4 VARIABLE B8 - DRYWELL SUMP LEVEL - Not provided. ' The Brunswick plant design does not require continuous measurement of drywell sump level. A LOCA signal will prevent operation of the '
sump pumps and will close containment isolation valves to eliminate the possibility of radio-active materials leaking outside the Pri ary Containment. During and after a LOCA, the drywell sumps overflow to the suppression pool.
i VARIABLE B9 - PRIMARY CONTAINMENT PRESSURE - RG 1.97 recommendations will be met by Variables A5 and A7. l l .
a 13 Rev. I a
)
l
-.-w ,
VARIABLE B10 - PRIMARY.CONTAINHENT lSOLATf0N VALVE POSITION 1 Recommended. J By RC 1.97 Provided By Brunswick .'
f- (s) Instrument Range Closed - Not Green indicating light - closed Closed Red indicating light - open e
$ (b) Environmental Yes Note 1 Qualification (c) Seismic Qualification Yes -Note 1 (d) Quality Assurance Yes Note 2
} l i (e) Power Supply lE lE (f) Redundance & Sensor - No No Location All sensors are located on the primary containment isolation valves.
(g) Location of' Display All the valves at the Brunswick plant involved in primary containment isolation that are air / solenoid or motor oper-ated are listed below by penetration number. All the panels I! listed are located in the main control room.
i 1
li l* Penetration No. Valve Tag No. Location of Display i.
3B .CAC-V49# XU-51 ,
- l. -3B CAC-V50f XU-51 l 1 7A B21-F022A H12-P601 {
? 7B B21-F022B l 7C B21-F022C 7D B21-F022D ij 7A B21-F028A li 78 B21-F028B 7C B21-F028C 7D B21-F028D 8 B21-F016 8 B21-F019
. 9A B21-F032A H12-P603
"- 9A E41-F006 H12-P601 9B B21-F032B H12-P603' l
- 9B 9B E51-F013 C31-F042 H12-P601 H12-P603 14 Rev. 1
} VARIABLE B10 - PRIMARY CONTAINMENT ISOLATION VALVE POSITION (Cont'd) i.
-Penetration'No. Valve Tat No. Location 10 ~ E51-F007 H12-P601
-} 10 E51-F008 " "
11 E41-F002 "' "
f 11 E41-F003 " "
12 Ell-F009 " "
12 E11-F008- " "
13A E11-F015A " "
-13A E11-F017A " "
- 13B E11-F0158 " "
F 138 E11-70178 " "
14 C31-F001 " "
L, 14 C31-F004 " "
p -16A' E21-F005A. " "
16B E21-F004A " "
16B E21-F005B " "
16B E21-F004B " "
'. 17 Ell-F022 " "
1 17 E11-F023 "' "
18 C16-F003 " "
, 18 C16-F004 " "
. 19 C16-F019 " "
19 C16-F020 " "
i 23 RCC-V-52 XU-3 j 24 RCC-V-28 "
9 25 CAC-V6 XU-51 j 25 CAC-V15 "
l 25 CAC-V55# "
1 25
- CAC-V56f "
.; 25 CAC-V48# "
j 25 CAC-V4 " '
26 CAC-V9 "
26 CAC-V10 "
26 CAC-V23 XU-56 j 35A TIP-V1 H12-P601 35B TIP-V2 "
35C TIP-V3 "
i 35D TIP-V4 "
39A E11-F016A "
4 15 - $
=
VARIABLE BIO - PRIMARY CONTAINNENT ISOLATION VALVE POSITION (Cont'd)
J Penetration No.- ' Valve Tag No. Location U
39A E11-FG21A H12-P601 l' E11-F016B 39B " "'
39B' Ell-F021B 498 CAC-PV-12005 XU-2
]; CAC-PV-1261 49B ~ "
51A . Ell-F043C "
515 E11-F043A
. SIC Ell-F037C "
l 51D- E11-F037A "
SIE (Spared) B21-PV-1212E
{ "
' 53A B21-F049C
" l
'53B .B21-F047C '
53C B21-F046A 53D B21-F008 "
53E B21-F040 ,
53F. B21-F048A "
54A B21-F014B 54B. B21-F014A 54C B21-F014E i 54D B21-F014F 54E CAC-PV-3439 "
!j! 54E CAC-PV-1211E l "
l; - 54E CAC-PV-3438 54E 'CAC-PV-3437 '
54F CAC-PV-1262 f 54F CAC-PV-1211F.
- j 55 RNA-V101 XU-51 l1 56A B21-F014K XU-2 ll "
56B B21-F014J ll "
56C B21-F014N 56D B21-F014P 56E (Spared) B32-F019 H12-P603 56E B32-F020 56F (Spared) B23-PV-1210F XU-2
57A CAC-PV-1209A 57A CAC-SV-1263-4
- 57B CAC-PV-1209B 57B CAC-SV-1263-3
- 16 Rev. 1
VARIABLE C10'-lPRINARY CONTAINMENT ISOLATION VALVE POSITION ~(Cont'd) i Valve Tan No.- Location Penetration-No..
B21-PV-1209C XU-2 57C (Sparad). "
57D CAC-PV-1209D "
-57E (Spared)~ B21-PV-1209E' "
57F (Spared) B21-PV-1209F " ,
58A B21-F058N '"
- 583 B21-F052C "
58C B21-F058R "
158E B21-F058T "
58F B21-F050C "
59A B21-F050A "
59B B21-F058C "
59C B21-F058C "
1-59D, 2-58D L21-F058A "
1-58D, 2-59D B21-F058L "
59E B21-F058E "
t B21-F052A
" 59F "
('I l- 60A (Spared) B32-F056F "
60B (Spared) B32-F056C "
60C- E41-F023A "
50D .E41-F023C "
,!. -60E CAC-PV-1205E "
CAC-SV-1263-2 * ,
i 60E 60F (Spared) B21-PV-1205F
.l B21-F056 I) 61A "
61B B21-F054 "
61C (Spared) B32-F056H "
610 (Spared) B32-F056A "
61E ,
E51-F043C "
61F E51-F043A "
62A B32-V22 "
l' 62B IA-PV-1204B "
62C IA-PV-1204C "
q l-68A, 2-68C Ell-F037D "
l-680, 2-68A E11-F043D "
68B Ell-F043B "
68D Ell-F037B "
- { B21-PV-1229E 68E (Spared) "
]
u 68F (Spared) B21-PV-1229F "
69A B21-F042B Rev. 1 17
VARIABLE B10 - PRIMARY COPTAINMENT ISILATION VALVE POSITION (Colt'd)'
Penetration No. ' Valve Tag No. Location 69B -B21-F044B XU-2 69C .B21-F046B " l 69D B21-F0488 "
69E IA-PV-1217E "
1-69F, 2-Spared B21-F049D "
) 70A E41-F023D "
I 708 E41-F023B "
70C B32-F056C "
70D B32-F056B " l 70E (Spared) B21-PV-1228E "
.70F (Spared) B21-PV-1228F 71 RNA-V103 XU-51 '
72A B32-F056E XU-2 72B B21-F060 "
72C (Spared) B21-PV-1226C -
72b B32-F056D "
! 72E E51-F043D '
72F E51-F0435
[ CAC-PV-1227A 73A "
l 73A CAC-SV-1259-4 * "
73B CAC-PV-1227B
[ * "
l 73B CAC-SV-1259-3* "
73C CAC-PV-1227C l "
1-73C, 2-71E CAC-SV-1259-2 * "
l 1-73E, 2-73C CAC-PV-1260 "
l E21-F017B l 73D "
CAC-PV-1227E {
73E "
73F - B21-PV-1227F "
74A B21-F058P "
74B B21-F058S 74C B21-F052D "
74D B21-F050D 74E B21-F058M "
74F B21-F058U ,
1-75A, 2-75D B21-F050B " '
3 75B B21-7058H 75C B21-F058D "
1-75D, 2-75A B21-F052B 18 Rev. l'
VARIABLE B10 - PRIMARY CONTAINMENT ISOLATION VALVE POSITION (Cont'd)
Penetration No. Valve Tag No. Location i 75E B21-F0588 XU-2 j 75F B21-F058F 76A- B21-F014L 76B CAC-PV-L225B ;
- 76B CAC-PV-3440 76B CtfrPV-3441 76B CAC-PV-3442 76C CAC-PV-1225C 76D B21-F014S.
76E B21-F014R
] B21-F014M ll 76F
] 77A B21-F014C
!; 77B RCC-PV-1222B XU-3 ,
77C RCC-PV-1222C
! 77D B21-F014H XU-2 1 77E B21-F014C j 77F B21-F014D j 78A B32-V30
- H12-P603 1
82A (Spared) IA-PV-1201A XU-2 3 82B B21-F042A l 1 82C E21-F017A 82D B21-F044A 205 CAC-V5 XU-51 205 CAC-V47 i j 205 CAC-V16 205 CAC-V17
] , CAC-SV-1218A 4 206A/A XU-2
} 206A/C CAC-PV-1218C 206A/D E41-PV-1218D 206B/B CAC-PV-1219B '
206B/C CAC-PV-1219C 206B/D E41-PV-1219D 206C/C CAC-PV-1220C 206C/D E41-PV-1220D 206D/C CAC-PV-1221C 206D/D E41-FV-1221D ,
t 209B/A CAC-SV-1213A 2-209B/B RXS-SV-4188 XU-75 19 Rev. 1
VARIABLE B10 '- PRIMARY CONTAINMENT ISOLATION VALVE POSITION (Colt'd)
Penetration No. Valve Tag No. Location' 2-209B/L' RXS-SV-4189 XU-79 2-209B/D RXS-SV-4186 XU-75 2-209B/D RXS-SV-4187 XU-79
. 210A' E11-F024A H12-P601
.i 210A' Ell-F007A' " "
l' ' 210A Ell-Fella-2108 Ell-F024B- " "
- 210B E41-F012 " "
210B E51-F019 "
210B E11-F007E "
l 210B E11-F011B '" "
211A E11-F027A-k " "
211A Ell-F028A " "
211B Ell-F0278 " "
211B E11-F028B E11-F103B l 214 " "
214 Ell-F103A " "
- l E51-F066 216 " "
216 E51-F062 " " 4 218 E41-F079 " !
218 E41-F075 l XU-2
' -220 CAC-V7 220 CAC-V8 XU-2 '
l ll XU-2 220 CAC-V22 lt H12-P601 223A E21-F015A "
L "
Y, 223A E21-F031A "
2235 E21-F031B g 223B -
E21-F015B 224 E51-F031 " "
225A E11-F020A "
L! 225B Ell-F020B " "
- l. 226 E41-F042 "
I' 227A 'E21-F001B " "
227B E21-F001B 1-231 TD-V4 XU-3 1 2-231 TD-V22:
241 B32-F039B XU-2 li 241B B32-F058B 241C B32-F006B' "
241D B32-F005B
" 20 . Rev. I 1 .
I;
r
, VARIABLE B10 - PRIMARY CONTAINMENT. ISOLATION. VALVE POSITION -(Cont'd) ,
Penetration No. Valve Tag No. Location of Display
,. 241F' B32-F039D XU-2
- 1-243A, 2-243D B32-F0423 l'
1-243D, 2-243A B32-F041B i 1-243E, 2-243F B32-F041A 1-243F, 2-243E B32-F042A j 244A B32-F041C.
! 244B car-PV-1231B 244B CAC-SV-1259-1*
t '244D B32-F042C 244E B32-F042D 244F- B32-F041D l l 245A B32-F039C l l 245B B32-F058A l
" ~
'245C B32-F006A !
! 245D~ B32-F005A l 245F CAC-PV-1215E -
p 245F CAC-SV-1263-1*
! 245F B32-F039A i
i' NOTES: PM 82-237, 288 involve replacement of some reactor instrument penetration (RIP) valves.
All RIP valves are included in the above list.
Limit switch, flow switch, and position switch qualification for primary containment u
isolation valves is belhg done by the 79-01B task force.,
- Indf ,ates the valve has been deleted on U1 by PM 80-032 and will be deleted on U2 by PM 80-033 during the next outage of sufficient duration to accomplish the work.
- PM's80-133, 134 are replacing the air operators and/or the solenoid valves on these
' valves with qualified solenoid valves.
i
-! h) Schedule: PM 82-287 (U1) is to be scheduled to be completed during refueling outage #5 and PM 82-288 j (U2) by March 1985. PM 80-133 (U1) is scheduled to be completed during refueling outage #4 and I
. PM 80-134 will be scheduled for completion on the next outage of sufficient duration to accomplish the work.
1 21 Rev. 1 i
a
__.-m . _ _ _ _ _ __.__.___ _ _ . _ _ _ _ _ _ _ ._ _
T]
VARIABLE C1 - RADIOACTIVITY CONCENTRATION OR RADIATION LEVEL IN CIRCULATING PRIMARY COOLANT Recommended by RC 1.97 Provided by Brunswick 6 (a) Instrument Range 1/2 Tech Spec. Limit to 100 Brunswick meet required Times Tech Spec. Limit Range Yes Yes (Sampling System)
(b) Environmental Qualification Yes Yes (Sampling System)
(c) Seismic Qualification (d) Quality Assurance Yes Yes (Sampling System) l (e) Power Supply lE lE (Sampling System)
Yes Yes (f) Redundance & Sensor Location Primary coolant samples are taken from the Reactor Water Cleanup System during normal operation and analyzed .
at the counting room by an ND 6620 system. During accident situations, Primary Coolant samples are taken
- by the Post Accident Sampling System located outside the Reactor Building. The sample is analyzed by the HD 6620 system in the counting room. A portable ND 66 is available to do analysis and a mobile station equipped with an ND 6620 is available. The Technical Support Center will also have an ND-66 linked to the ,
> ND 6620 in the counting room. Radiation level is logged and the results are phoned in to the Control Room and logged by the Operator.
(g) Location of Display - Counting Room, Mobile Station (h) Schedule - TMI Plant Modifications80-028'and 80-029 have provided the POST ACCIDENT SAMPLING SYSTEM for Unit I and 2 respectively.
22 Rev. 1 i
}'
t, VARIABLE C2 - ANALYSIS OF PKIMARY COOLANT (CAMA SPECTRUM)
' Recommended by. ,
- Provided by Brunswick RC 1.97 l'
(a) Instrument Range 10 ' Ci/gm to 10 Ci/gm or 4
TID-14d44 Source. Term in Cooiant Volume Brunswick meets required range j_
No Yes (Sampling System)
(b) . Environmental Qualification Yes (Sampling System)
(c) Seismic Qualification No l
I (d) Quality Assurance High Quality Commercial Grade Yes (Sampling System) i (e) Power Supply Non.1E 1E (Sampling System) l No Yes (f) Redundance & Sensor Location
)
- ' Primary coolant samples are taken from the Reactor Water Cleanup System during normal operation and analyzed at the Counting Room by an ND 6620 system. During accident situations Primary Coolant samples are taken by the Post Accident Sampling System located outside the Reactor Building. The ll sample is analyzed by the ND 6620 system in the Counting Room. A portable ND 66 is available to
- do analysis and a mobile station equipped with an ND 6620 is available. The Technical Support Center b will also have an ND-66 linked to the ND 6620 in the counting room. Radiation level is logged and the results are phoned in to the Control Room end logged by.the Operator.
(g) Location of Display - Counting Room .Nobile Station (h) Schedule - D11 Plant Modifications80-028 and 80-029 have provided the Post Accident ff l' Sampling System for Unit 1 and 2, respectively.
1 it
'1 23 Rev. 1
d f
Variable C3 - BWR Core Temperature - Not required at this time yer NUREC 0737 Supplement 1. -
Variable C4 -
RCS Preasure - RC 1.97_reco6mendations will be met by Variable A1.
f Variable C5 - Primary.Contanzent Area Radiation - RG 1.97 recommendations will be met by Variable El.
See discussion for Variable El.
I Variable C6 - Drywell Drain Sumps Level - Not required. See diccussion for Variable 88.
. Variable C7 - Suppression Pool Water Level - RG 1.97 recommer dations will- be met by Variable A4.
Variable C8 - Drywell Pressure - RC 1.97. recommendations will be met by Variable A5.
Variable C9 - RCS Pressure - in 1.97 recommendatior.s will be met by Variable A1.
Variable C10 - Primary Containment Pressure - RG 1.97 recommendations will be met by variables A5 & A7.
l Variable Cll - Containment and Drywell Hydrogen Concentration - RG 1.97 recommendations will be met by Variable A8.
Variable C12 - Containment and Drywell Oxygen Concentration - RG 1.97 recommendations will be met by Variable A8. .
Variable C13 - Containment Effluent Readioactivity-Nable Cases -. RC 1.97 recommendations will be met by variables E4 and E5.
Variable Cl4 - Radiation Exposure Rate - Not required at this time per NUREC'0737 Supplement 1.
Variable C15 - Effluent Radioactivity - RC 1.97 recommendations will be met by Variables E4 and E5.
24 Rev. 1 t
9
t VARIABLE D1 - NAIN FEEDilATER FLOW Recommended by RC J.97 Provided by Brunswick a) Instrument Range 0-110% design 0-109.8% (0-12,000,000 f/Hr.
, b) Environmental-Qualification, No Yes ',
c) Seismic Qualification No' Note 1 d) Quality Assurance No . Note 2 e) Power Supply Non-1E High Reliability f) Redundance & Sensor Location No No -
Sensor Tag Number Range Location Flow Element C32-FE-N001A 0 to 6 x 106'#/hr Nain FW line 9-18-B-1 Flow Element C32-FE-N0018. 0 to 6 x 10 f/hr Nain FW line 8-18-B-1 Flow Transnitter C32-FT-N002A 0 to 6 x 10 f/hr IR-TB-8 6
Flow Transmitter -C32-FT-N002-5 0 to 6 x 10 f/hr- IR-TB-8 2-(g) Location of Display Display Tag Number Range location 6
Indicator C32-FI-R604A 0 to 6 x 10 f/hr H12-P603 Control Room Indicator C32-FI-R604B 0 to 6 x 10 6f/hr H12-P603 Control Room Recorder C32-FR-R607 0 to 12 x 10 f/hr H12-P603 Control Room (h) Schedule -- No changes to the instrumentation are required.
l 25 . Rev. 1 I
l
] .i
'! VARIABLE D2 - CONDENSATE STORACE TANK LEVEL
' - Recosamended by RG 1.97 Provided by Brunswick (a) Instrument Range Top to Botton 0-100%
- (b) Environmental Qualification No Note 1 e
(c) Seismic Qualification No Note 1 l
I (d) Quality /saurance No Note 2 (e) Power Supply Non-lE High Reliability I
(f) Redundance & Sensor Location No No Sensor Tag Number Range Location Level Trant,aitter CO-LT-3473 0-100% Local Y (g) Location of Display i Disolay Tag Number Range Location
, Indicator CD-LI-1160A 0-100% XU-2 Control Room Indicator CO-LI-1160B 0-100% Radwaste Pal. C16-P001 (h) Schedule - No changes are required f
i j 26 Rev. 1 l}
e 4
_ _ _ -.- __-_-_ _. ____ _ .______ .___A______________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _
~
+
l' J
i 4
VARIABLE D3 - Suppression Spray Flow I! Brunswick does not intend to provide this variable. RHR' flow can be used to monitor l
the operation of primary containment related systems.. Drywell pressure, drywell
! temperature, suppression pool pressure and suppression pool temperature give indica-
- tion that the safety systems are accomplishing their tasks. These variables are
!. provided at Brunswick.
lI '
l l1 L
II li l l': !
l!
l lI
't i
li tt L. .
( s' 27 Rev. 1 li Il
VARIABLE D4 - DRYWELL PRESSURE Recommended to RC 1.,97 Provided by Brunswick a) Instrument Range Harrow range -2.7 to + 3 p:1g 0 to + 2 psig l Wide range O to 110% design pressure See Variable AS b) Environmental Narrow range Yes No Wide range Yes See Variable A5
, c) Seismic Qualification Narrow range No No i
Wide range No See Variable A5 d) Quality Assurance Narrow range Yes Note 2 Wide range Yes See Variable AS e) Power Supply Harrow range Non-lE Non-lE Wide range Non-lE See Variable A5
, f) Redundance & Sensor Location No No Sensor Tag Number Range location Narrow Range Transmitter CAC-PT-2685 0to+2 Local Wide Range - See Variable A5 Transmitter g) Location of Display I Display Tag Number Range Location Natrow Range Indicator / Controller CAC-PIC-2685 0 to + 2 psig XU-51 control Room l' -
Wide Range See Variable A5 Display h) Schedule Brunswick will install a new transmitter and indicator with a -5 to +3 psig range Unit I work will be scheduled for completion during refueling outage #5 and Unit 2 work will be scheduled for completion during refueling outage #6.
28 Rev. 1
A> N IMAGE EVALUATION [j/f t:8
'I#4
% f)
/ 1[. f/// TEST TARGET (MT-3) Y W/
y/p%/ %<,;g[ l l.0 ll1En M
& 9 B1s l-l $$S j l.8 1.25 1 1.4 1.6 l
4 150mm >
< 6" >
4 *# 'b '
49
% o i>4* 7 &>a/b v
<+4+s,
////h
- x .
t o? > h IMAGE EVALUATION Qf0 fI*# ,
4
/\t@f f//
//o TEST TARGET (MT-3) (( Y / , & #4, B
1.0 it2 En 11 ii 5)9 2:ils
( ~ En1.8 1.25 i.4 i.6 4 150mm >
4- 6" >
- ? #
f I$ 4;.
+,///
n
l i I VARIEBLE DS - Suppression Pool Water Level -
RC 1.97 recommendations for this variable will be
]' met by variable A4.
VARIABLE D6 - Suppression Pool Water Temperature - RG 1.97 recommendations for this variable will j be met by Variable A3.
- I l VARIABLE D7 - Drywell Atmosphere Temperature - RG 1.97 .ecommendations for this variable will be i met by Variable A6.
VARIABLE D8 - Drywell Spray Flow - Brunswick does not intend to provide this variable '
for the same reasons given for variable D3.
VARIABLE D9 - MSIV Leakage Control System Pressure - Not Required. This system is not included in
- ) the Brunswick design.
i 1
6 f
29 Rev. 1 9
VARIABLE D10 - PRIMARY SYSTEM SAFETY RELIEF VALVE POSITION Recommended by RG 1.97 Provided by Brunswick a)' Instrument Range Closed - Not Closed Green Indicating light - Closed Red Indicating light - Open
'l Environmental Qualificatica
- b) Yes The NDT International flow
!; transmitters used at Brunswick j are currently undergoing environ-
! mental qualification at Wyle Laboratories.
c) Seismic Qualification No Yes
, d) Quality Assurance Yes Note 2 ,
e) Power Supply Non-lE High quality f) Redundance & Sensor Locatict No No Sensor Tag Number Range Location s
- Transmitter B21-FT-4157 Closed-not closed VLV F013A
! Transmitter B21-FT-4158 Closed-not closed VLV F013B
{ Transmitter B21-FT-4159 Closed-not closed VLV F013C l Transmitter B21-FT-4160 Closed-not closed VLV F013D j Transmitter B21-FT-4161 Closed-not closed VLV F013E Transmitter B21-FT-4162 Closed-not closed VLV F013F Transmitter B21-FT-4163 Closed-not closed VLV F013G Transmitter B21-FT-4164 Closed-not closed VLV F013H Transmitter B21-FT-4165 Closed-not closed VLV F013J
- Transmitter B21-FT-4166 Closed-not closed VLV F013K Transmitter B21-FT-4167 Closed-not closed VLV F013L 4
30 Rev. 1
)
- b ,
- (
VARIABLE D10 - PRIMARY SYSTEM SAPETY RELIEF VALVE POSITION (Continued)
- l i g) Location of Display
, Display Tag Number Range ~ Location ,
ll Indicator light B21-D51A Green H12-P601 Control Room
- !. Indicator light B21-D52A Red H12-P601 Control Roon .
lj Indicator light B21-D51B Green H12-P601 Control Room Indicator light B21-D52B Red H12-P601 Control Room Indicator light B21-D51C Creen H12-P601 Control Room ,
,i Indicator' light B21-D52C Red H12-P601 Control Room *
't Indicator light B21-D51D Creen H12-P601 Control Room Indicator light B21-D52D Red 'H12-P601 Control Room -
Indicator light B21-D51E Creen H12-P601 Control Room Indicator light B21-D52E . Red H12-P601 Control Room Indicator light B21-D51F Creen H12-P601 Control Room Indicator light B21-D52F Red H12-P601 Control Room a Indicator light B21-D51G Green H12-P601 Control Room Indicator light B21-D52C Red H12-P601 Control Room -
i Indicator light B21-D51H Creen H12-P601 Control Room Indicator light B21-D52H Red H12-P601 Control Room '
! Indicator light B21-D51J Creen H12-P601 Control Room Indicator light B21-D52J Red H12-P601 Control Room Indicator light B21-D51K Creen H12-P601 Control Room Indicator light B21-D52K Red H12-P601 Control Room Indicator light B21-D51L, Green H12-P601 Control Room B21-D52L H12-P601 Control Room Indicator light - Red h) Schedule: Should replacement of the transmitters prove necessary,79-01B scope will replace them with qualified transmitters on a schedule consiatent with IE Bulletin 79-01B
,; and 10CFR 50.49.
! s 31 Rev. 1 9
m l$
1
Y e
i VARIABLE Dil - ISOLATION CONDENSER SYSTEM SHELL-SIDE WATER LEVEL
.: I, .
] This. variable is not. required.. This system is not included in the Brunswick design.
VARIABLE D12 - IS0!3 TION CONDENSER SYSTEM VALVE POSITION This variable 'is not required. This system is not included in the Brunswick design.
?
e 1
,f Ih 1;
14
- f. s ll 32 Rev. 1 u
'?,
)
.i
..o ' .
VARIABLE D13 - RCIC FLOW CONTROL Recommended By Provided by Brunswick
- i .RG 1.97
't (a) Instrument Range O to 110% 0 to 110% design flow
]- design flow (b) Environmental Qualification Yes Note 1
- j. (c) Seismic Qualification No Note 1 il
- t (d) Quality Assurance Yes Note 2 (e) Power Supply Non-lE lE (f) Redundance & Sensor No No Location
'i
- f Sensor Tag Number Range Location
.l *
- I Flow Element E51-FE-N001 0-450" Water Col. RCIC Pump Discharge line Flow Transmitter E51-FT-N003 0-450" Water Col. E51-2-4-605 (g) Location of Display Display Tag Number Range Location ,
, Flow Indicator / E51-FIC'-R600 0-500 gpm H12-P601 Control Room li Controller (h) Schedule: Transmitter E51-FT-N003 will be replaced to comply with environmental
,. qualification on a schedule consistent with IE Bulletin 79-OlB and 10CFR50.49.
, i i
33 Rev. 1
VARIABLE D14 - HPCI FLOW Recommended By Provided By Brunswick RC-1.97 (a) Instrument Range O to 110% 0 to 110% design flow design flow .
{ (b)' Environmental Qualification Yes No, to be provided by'PM 82-263, 264 (c) Seismic Qualification No Note 1 (d) Quality Assurance Ye.s Note 2 i
(e) Power Supply Non-lE lE p (f) Redundance & Sensor No No Location Sensor Tag Number Range Location Flow Element E41-FE-N007 0-5000 gpm HPCI Pump Discharge Line E41-2-14-605 Flow Transmitter E41-FT-N008 0-5000 gpa H21-P014 (g) location of Display ;
Display Tag Number Range Location Flow Indicator / E41-FIC-R600 0-5000 gpm H12-P601 Control Room Controller (h) Schedule: There are no changes required for the basic instrument loop. Plant modifications82-263, and 82-264 are to replace the transmitters to comply with environmental qualification on a schedule consistent with IE Bulletin 79-01B and 10CFR50.49.
34 Rev. 1 4 L
! r ll lt ,
VARIABLE D15 - CORE SPRAY SYSTEM FLOW Recommended by Provided by Brunswick
- i RG 1.97 (a) _ Instrument Range O to 110%' 0 to-110% design flow, O to 5198 gpm design flow 3, (b) Environmental Qualification Yes Note 1 i, (c) Seismic Qualification No
- Note 1 l
ji (d) Quality Assurance Yes Nute 2 il (e) Power Supply . Non-1E lE (f) Redundance & Sensor No No '
Location-Sensor Tag Number Range Location Flow Element E21-FE-N002A 0-638" water Col. CS pump line E21-2-12-300 Flow Element E21-FE-N002B " " " " CS pump line E21-6-12-300
" " " " H21-P001 Reactor Bldg.
Transmitter E21-FT-N003A H21-P019 Reactor Bldg.
Transmitter E21-FT-N003B
- I' (g) Location of Display
]i Display jrag Number Range Location ,
, Flow Indicator E21-FI-R601A 0-7000 gpm H12-P601 Control Room I -- Flow Indicator E21-FI-R601B 1 .
,. (h) Schedule: Transmitters E21-FT-NO33A and E21-FT-N003B will be replaced to comply with
- 4: environmental qualification on a schedule consistent with IE Bulletin 79-01B and 10CFR50.49. '
l.
- 35 Rev. 1
_m __ _ _ _ _ _ -__
VARIABLE D16 - LPC1 SYSTEM FLOW Low pressure coolant injection is a mode of 'the RHR (Residual Heat Removal) syaten. Low pressure cooling systems at Brunswick include the Core Spray System and the RHR system. Refer to variables D15 and D19.
t VARIABLE D17 - SLCS FLOli Refer to Brunswick Position Paper paragraph 4.4.13. -
G E
36 Rev. 1
i VARIABLE D18 - SLCS STORAGE TANK LEVEL Recommended by Provided by Brunswick RG 1.97 (a) Instrumet. Range Bottom to Top 0 to 100% (Bottom to Top)
'! (b) Environmental Qualification Yes No, per category 3 designation in Brunswick Position Paper on RG 1.97 ls (c) Seismic Qualification No Note 1 Note 2 (d) Quality Assurance No
,f (e) Power Supply -
Non-lE lE (f) Redundance Sensor No No Location Sensor Tag Number Range Location Level, Transmitter C41-LT-NG01 0-200 in, water H21-P001 Reactor Bldg.
.{
- l (g) Location of Dioplay '
lI
Display Tag Number Range Locat109 Indicator C41-LI-R601 0-100% H12-P603 Control Room (h) Schedule: No changes to the. instrument loop are required.
- e .
1 1
.i 37 Rev. 1 k
(
a
.t II l VARIABLE D19 - RHR SYSTEM FLOW Recomunended by Providad by Brunswick RG 1.97
- { (a) Instrument Range 0 to 110% 0 to 110% design flow, O to 22,290 gpm design flow I
- (b) Environmental Qualification Yes Note 1 (c) Seismic Qualification No Note 1 (d) Quality Assurance Yes Note 2 (e) Power. Supply Non-lE 1E (f) Redundance and Sensor No No i Location Sensor Tag Number Range Location d
Flow Element Ell-FE-N014A 0-25,000 gpm Pipe Ell-18-20-300 Reactor Bldg.
Flow Element Ell-FE-N014B Pipe Ell-21-20-300 Reactot Bldg.
Flow Transmitter E11-FT-N015A 0-30,000 gpa Rack H21-P018 Reactor B1dg.
jj Flow Transmitter Ell-FT-N015B " " " Rack H21-P021 Reactor Bldg.
j (g) Location of Display Display Tag' Number Range Location 1
Flow Indicator Ell-FI-R603A 0-30,000 gpm H12-P601 Control Room Flow Indicator Ell-FI-R6038
.; (h) Schedule: Transmitters Ell-FT-N015A and Ell-FT-NOISB will be replaced to comply with
- i environmental qualification on.a schedule consistent with IE Bulletin 79-OlB and 10CFR50.49.
38 Rev. 1
- VARIABLE D20 - RHR HEAT EXCHANCER OUTLET TEMPERATURE .
Recommsended by Provided by Brunswick
, RC 1.97 (a) Instrument Range 32 to 350 F 0 - 600 F
- j. (b) Environmental Qualification Yes Note 1 (c) Seismic Qualification No' Note 1 l
(d) Quality Assurance Yes Note 2 l- (e) Power Supply Non-lE lE i
I (f) Redundance & Sensor No No I
Location i
1 .
Sensor Tag Number Range Locat'on i Temperature Element Ell-TE-N027A 0-600 F Pipe Ell-18-20-300 Reactor Bldg.
Temperature Element Ell-TE-N0278 0-600 F' Pipe Ell-21-20-300 Reactor Bldg.
(g) Iocation of Display Display Tag Number Range Location Recorder E41-TR-R605 0-600 F H12-P614 Control Room (h) Schedule: Temperature elements Ell-TE-N027A and Ell-TE-NO27B will be replaced to comply with environmental qualification on a schedule consistent with IE Bulletin 79-OlB and 3 10CFR50.49.
39 Rev. 1
4 5
= S
+
j VARIABLE D21 - COOLING MATER TEMPERATURE TO ESF SYSTEN C(MPONENTS ' l
- j Brunswick does not intend to provide this variable. See Brunswick Position Paper on RG.1.97
- f paragraph 4.4.17. ,
1
- g
!( .
3 8
a 99
~
- )
44
?
t.
e e
i .
40 Rev. 1 g.,
i I 8 6
I
, ,a
t e i- VARIABLE D22 - COOLING WATER FIDW TO ESF SYSTEM COMPONENTS Recommended by Provided by Brunswick l RC 1.97 i
f (a) Instrument Range O to 110% 0 to 150%, O to 12,000 gpm for RHR Service design flow water. There are no flow Indicators on the seal cooling exchangers, RHR pump room cooler, or Core spray fan cooling units.
(b) Environmental Qualification Yes Note 1 4
(c) Seismic Qualification No Note 1 j (d) Quality Assurance Yes Note 2 I
- (e) Power Supply Non-lE lE for AHR Service Water Flow only.
4 (f) Redundance / Sensor Location No No i
ESF Component Sensor Tag Number Range Location RHR Heat Exchangers Flow Transmitter E11-FT-N007A 0-800 in. water H21-P018 Rx. Bldg.
" " " " " " H21-P021 Rx. Bldg.
Service Water Flow E11-FT-N007h Sealing Cooling Exch. Flow Switch SW-FEL-834 Low Flow Pipe SW-135-1-157A
" " " " " " " " " Pipe SW-130-1-157A SW-FSL-835
" " " " " " " " " Pipe SW-136-1-157A SW-FSL-836
" " " " " " " " " Pipe SW-129-1-157A SW-FSL-825 Fan Cooling Units CS Pump Roon "lA" Pressure Switch SW-PSL-1174 Low Pressure Pipe SW-116-2-157A
" " " " " Pipe SW-123-6-157 Pump Room "lB" SW-FSL-1178 RHR Pump Room Coolers t 1B, 2A Not Applicable I
41 Rev. 1 8
b VARIABLE D22 - Continued (g) Location of. Display ESF Component Display- Tag Number Range Location t
i RHR Heat Exchangers Indicator Ell-FI-R602A. 0-12,000 gpm H12-P601 Control Ra.
~" " " " " " "
Service Water Flow Ell-FI-R602B Seal Cooling Exchangers RHR Pump 1A Annunciator UA-Al Low Flow H12-P601 Control Ra, 1B UA-Al J 1C UA-Al l " 1D " "
UA-Al M
Fan Cooling Units CS Pump Re.,a "lA" Annunciator UA-5 Low Pressure XU-3, Control Room j "lB" " "
UA-5 " " " " " "
1 ,
RHR Pump Roon j Coolers 1B, 2A Not Applicable I
(h) Schedule: Brunswick will provide flow instrumentation for the conventional and nuclear service water i p header lines SW-100-24-157 and SW-103-30-157 respectively. Work for Unit I will be g scheduled for completion'during refueling outage #5 and work for Unit 2 will be scheduled
, for completion during outage #6. Transmitters E11-FT-N007A and Ell-FT-N007B will be
]:
replaced to comply with environmental qualification on a schedule consistent with IE ,
Bulletin 79-dlB and 10CFR50.49. '
1 l-I r
'l i
[ 42 Rev. 1 l
VARIABLE D23 - hIGH RADI0 ACTIVITY LIQUID TANK LEVEL Recommended by Provided by Brunswick RG 1.97 (a) Instrument Range Top to Botton Top.to Bottom, 0 - 100%
(b). Environmental Qualification No Note 1 (c) Seismic Qualification No Note 1 (d) Quality Assurance No Note 2 (e) Power Supply Non-1E Conventional Power Supply (f) Redundance / Sensor No No I' Location
~
i Sensor Tag Number Range Location Transmitter C16-LT-N026 0-190" Waste Collector Tank A002 Radwaste Bldg.
, (g) Location of Display ,
7 Display Tag Number Range Location Recorder - Alarm G16-LRS-R008 0-100% P001 Radwaste Control Room (h) Schedule: No changes are' required to the existing instrumentation.
43 Rev. 1 l
VARIABLE D24 - EMERCENCY VENTILATION DAMPER POSITION Recommended by .
Provided by Brunswick RC 1.97 (a) Instrument' Range Open - Closed -
Open - Closed (b) Environmental Qualifi- Yes Note 1 cation (c) Seismic Qualification .No Note 1 (d) Quality Assurance Yes Note 2 (e) Power Supply Non-1E lE (f) Redundance /Scusor No No
] Location
'l 3
Sensor Tag Number Range Location j Position Switch 2-VA-ZS-916B Open-Closed Emergency Makeup Damper 2L-D-CB Control Bldg.
Position Switch 2-VA-BS-916A Open-Closed Normal Make-up Damper 2L-D-CB-Control Bldg.
- Flow Switch 1-VA-FS-928A Off-On Cable Spreading Room Fan'lA-SF-CB Supply Duct- '
I Control Building Flow Switch 1-VA-FS-928B Off-On Cable Spreading Room Exhaust Fan lA-EF-CB Duct-
! Control Building Flow Switch 2-VA-FS-929A Off-On Cable Spreading Room Supply Fan 2A-SF-CB Duct-Control Building *
. Flow Switch 2-VA-FS-929B off-On Cable Spreading Room Exhaust Fan 2A-EF-CB Duct-
?! Control Building Flow Switch 2-VA-FS-918A Off-On Mechanical Equipment Room Supply Fan 2F-SF-h
~
CB Duct - Control Building d Flow Switch 2-VA-FS-918B Off-On Hechanical Equipment Room Exhaust Fan 4 . 2E-EF-CB Duct - Control Building l Flow Switch 2-VA-FS-915A Off-On Emer Recire Fan 2A-ERF-CB Duct-Control Bldg.
d Flow Switch 2-VA-FS-915B 0ff-On Emer Recirc Fan 2B-ERF-CB Duct-Control Bldg.
- i. Position Switch 2-VA-ZS-918B Open-closed Mechanical Equipment Room Exhaust Damper 2T-D-CB-Control Building 9
Position Switch 2-VA-ZS-918A Open-Closed Mechanical Equipment Room Supply Damper 2K-D-CB - Control Building d
H .
H t
li 44 Rev. 1 1
i
VARIABLE D24 - EHFRCENCY VENTILATION DAMPER POSITION' (C'ont'd)
Sensor Tag Number Range Location 2-VA-ZS-917 Open-Closed . Control Room' Exhaust Damper 2H-D-CB - Control Bldg.
Position Switch Emergency.Rectre Damper 2A-EAD-CB - Control Building
-Position Switch' 2-VA-ZS-915A Open-Closed 2-V A-ZS-915C Open-Closed. Emergency Recirc Damper 2C-EAD-CB - Control Building Position Switch . Emergency Recire Damper 2B-EAD-CB - Control Building Pomicion Switch
~
2-V A-ZS-915B Open-Closed 2-VA-ZS-915D Open-Closed Emergency Recirc Damper 2D-EAD-CB - Control Building Position Switch Cable Spreading Room Supply ran Damper 2B-D-CB-Control Bldg.
Position Switch 2-VA-ZS-929A Open-Closed i
2-VA-ZS-929B Open-Closed Cable' Spreading Room Exhaust Fan Damper 2E-D-CB-Control Bldg.
f Position Switch- Cable Spreading Room Supply Fan Damper IB-D-CB-Control Bldg.
Position Switch 1-VA-ZS-928A Open-Closed f cable Spreading Room Exhaust Fan Damper IE-D-CB-Control Bldg.
Position Switch 1-VA-ZS-928B Open-Closed LSO-R7-321 Open Reactor Building Supply Isolation Damper IA l Position Switch Reactor Building Supply Isolation Damper IA Position Switch LSC-RX-321 Closed t
Open Reactor Building Exhaust Isolation Damper 1C
,l Position Switch LSD-RX-321 Reactor Building Exhaust Isolation Damper IC Position Switch LSC-RX-321 Closed l
LSO-RX-321 Open Reactor Building Supply Isolation Damper IB l Position Switch Reactor Building Supply Isolation Damper IB Position Switch LSC-RX-321 Closed Open Reactor Building Exhaust Isolation Damper ID i Position Switch LSO-RX-321 Reactor Building Exhaust Isolation Damper ID i Position Switch LSC-RX-321 Closed Open-Closed Drywell Purge Valve IN-BFV-RB Open-Closed
- Position Switch -
- Drywell Pump Valve IA-BFV-RB open-Closed Position Switch - Open-Closed t 4
?
g) Location of Display q
Display Tag Number Location Function I
2VA-CS-918-1 .XU-3 Control Room Mechanical Equip Room Exhaust Damper Control Switch (a) 2T-D-CB-Open
& Light Assembly Mechanical Equipment Room Exhaust
" 2VA-CS-918-1 . XU-3 Control Room
' 2T-D-CB Closed
" 2VA-CS-918-1 XU-3 Control Room Hechanical Equip Room Exhaust Fan 2E-EF-CB - Running
" 2VA-CS-918-1 XU-3 Control Room Hechanical Equip Room Exhaust Fan ll 2E-EF-CB-Off a
" 2VA-CS-918-1 XU-3 Control Room Mechanical Equip Room Supply Damper l' 2K-D-CB Open
- i. Mechanical Equip Room Supply Damper
" 2VA-CS-918-1 XU-3 Control Room 2K-D-CB Closed 45 Rev. 1 i
~-.
e a
' VARIABLE D24 - EMERCENCY VENTILATION' DAMPER POSITION. (Cont'd) g) Location of Display-
[ Display tab Number Location Function
! (a) . .
l Control Switch 2-VA-CS-918-1 XU3-Control Room Mechanical Equip Room Supply Fan 2F-SF-CB Running i & Light Assa. 2-VA-C3-918-1 XU3-Control Room Mechanical Equip Room Supply Fan 2F-SF-CB Off 2-VA-CS-917-1 XU3-Control Room Control Room Exhaust Damper 2H-D-CB Open 2-VA-CS-917-1 XU3-Control Room Coctrol Room Exhaust Damper 2H-D-CB Closed 2-VA-CS-917-1 XU3-Control Room Control Room Exhaust Fan 2D-EF-CB Running 2-VA-CS-917-1 XU3-Control Room Control Room Exhaust Fan 2D-EF-CB Off
! (b) 2-VA-CS-915A XU3-Control Room Emergency Recirc Fan 2A-ERF-CB Dampers Open
" " XU3-Control Room Emergency Recire Fan 2A-ERF-CB Dampers Closed i
" " Emergency Recirc Fan 2A-ERF-CB Running
! XU3-Control Room
" " XU3-Control Room Emergency Recirc Fan 2A-ERF-CB Standby i l "
i 2-VA-CS-915B XU3-Control Room Emergency Recire Fan 2A-ERF-CB Dampers Open
" XU3-Control Room Emergency Recirc Fan 2B-ERF-CB Dampers Closed
! 2-VA-CS-915B (c)
Indicating Light Assa. IVA-ZL-915A XU3-Control Room Emergency Recire Fan 2A-ERF-CB Dampers Open
" Emergency Recirc Fan 2A-ERF-CB Dampers. Closed i lVA-ZL-915A XU3-Control Room
" XU3-Control Room Emergency Recirc Fan 2B-ERF-CB Dampers Open j 1VA-ZLo915B
" Emergency Recire Fan 2B-ERF-CB Dampers Closed 1VA-ZL-915B .XU3-Control Room i
" Emergency Makeup Damper 2J-D-CB Open lVA-ZL-916A XU3-Control Room [
IVA-ZL-916A IU3-Control Room ; Emergency Makeup Damper 2J-D-CB Closed *
" XU3-Control Room Normal Makeup Damper 2L-D-CB Open IVA-ZL-916B
" Normal Makeup Damper 2L-D-CB Closed IVA-ZL-916B XU3-Control Room (d)
XU3-Control Room U2 Cable Spreading Rm Supply Fan Damper 2B-D-CB-Open Control Switch 2VA-CS-929-1
" U2 Cable Spreading Rm Supply Fan Damper 2B-D-CB Closed Light Assa. XU3-Control Room a
" " U2 Cable Spreading Rm Exhaust Fan Damper 28-D-CB Open XU3-Control Roon
" " U2 Cable Spreading Rm Exhaust Fan Damper 2B-D-CB Closed XU3-Control Room
" " U2 Cable Spreading Rm Supply Fan 2A-SF-CB Running
' -XU3-Control Room
" " U2 Cable Spreading Rm Supply Fan 2A-SF-CB Off XU3-Control Roon
" " U2 Cable Spreading Rm Exhaust Fan 2A-EF-CB Running XU3-Control Room
" " U2 Cable Spreading Rm Exhaust Fan 2A-EF-CB Off j XU3-Control Room f
, 46 Rev. 1 o
n
'- m ne
9 VARIABLE D24 - EMERCENCY VENTILATION DAMPER POSITION _( Cont'd) e g) Location of Display (Cont'd)
Display Tag Number Location Function (d)
Control Switch IVA-CS-928-1 XU3-Control Room U-l Cable Spreading Rm Supply Fan Damper IB-C-DB Open
& Light Assably.
U-1 Cable Spreading Rm Supply Fan Damper IB-C-DB Closed i
' U-1 Cable Spreading Rm Exhaust Fan Damper lE-D-CB Open U-l Cable Spreading Rm Exhaust Fan Damper IE-D-CB Closed U-l Cable Spreading Rm Supply Fan lA-SF-CB Running U-l Cable Spreading Ra' Supply Fan lA-SF-CB Off U-l Cable Spreading Rm Exhaust Fan lA-EF-CB Running U-l Cable Spreading Rm Exhaust Fan lA-EF-CB Off VA-CS-1510 Reactor Beilding Supply Isolation Damper IA Open Reactor Building Supply Isolation Damper lA Closed Reactor Building Exhaust Isolation Damper 1C Open Reactor Building Exhaust Isolation Damper 1C Closed VA-CS-1512 Reactor Building Supply Isolation Damper 1B Open Reactor Building Supply Isolation Damper 1B Closed Reactor Building Exhaust Isolation Damper ID Open Reactor Building Exhaust Isolation Damper ID Closed VA-CS-1589 Reactor Building Purge Valve IN-BFV-RB Open-Closed Reactor Building Purge Valve IN-BFV-RB Open-Closed h) Cchedule: No changes required for this instrumentation.
a) On both Unit 1 and Unit 2 Panel b) On Unit 2 Panel only c) On Unit 1 Panel Only i d) Other Unit has indication, No Control 47 Rev. 1
h i:-
VARIABLE D25 - STATUS OF STANDBY POWER AND OTHER ENERGY SOURCES IMPORTANT TO SAFETY (ELECTRIC. HYDRAULIC. PNEUMATIC) <
Recommended by RC 1.97 Provided by Brunswick ,
i (a) Instrument Range Plant Specific See Section (g)
(b) Environmental Qualification Yes Note 1 i f
, (c) Seismic Qualification No Note 1 i
1 (d) Quality Assurance Yes Note'2 l
l (e) Power Supply Non-lE lE a
(f) Redundance No No (g) For simplicity and clarity of this report, the instrumentation for each diesel generator is presented by giving voltage indication followed by breaker indication. The same is done for the nonsal source feeders. These are followed by DC battery voltage instrumentation and instrument air pressure indication.
a 1
48 Rev. 1
VARIABLE D25 - STATUS GF STANDBY POWER AND OTHER ENERGY SOURCES IMPORTANT TO SAFETY ,
I (ELECTRIC. HYDRAULIC PNEUHATIC)
Sensor Location (Diesel Generator Voltage)
The ' sensors for the diesel generator voltages are potential transformers located at the respective diesel generators.
i Location of Display, Display Tag Numbers Range Location DG No. 1 Voltmeter DC-VM-1265 0-5,000 volts Panel XU-2 Control Room DG No. 2 Voltmeter DC-VM-1272 0-5,000 Volts Panel XU-2 Control Room DG No. 3 Voltmeter DC-VM-1279 0-5,000 Volts Panel XU-2 Control Room DG No. 4 Voltmeter DG-VM-1286 0-5,000 Volts Panel XU-2 Control Room Sensor Locacion (Diesel Generator Breakers to Emergency Buses)
Breaker No. Sensor Location AE9 (DG No. 1 to Bus El) Breaker Auxiliary Contact 4160V SWGR El Compt. AE9 AG7 (DG No. 2 to Bus E2) Breaker Auxiliary Contact 4160V SWCR E2 Compt. AG7 AI5 (DC No. 3 to. Bus E3) Breaker Auxiliary Contact 4160V SWCR E3 Compt. AIS AK2 (DC No. 4 to Bus E4) Breaker Auxiliary Contact 4160V SWGR E4 Compt. LK2 Location of Display Breaker No. Display Tag Number Range Location AE9 Position Light EB-CS-950 Green light-open Panel XU-2, C'ntrol o Room Red light-closed AG7 Position Light EB-CS-957 Green light-open Panel XU-2, Control Room Red light-closed .
AIS Position Light EB-CS-952 Green light-open Panel XU-2, Control Room Red light-closed AK2 Position Light EB-CS-968 Green light-open Panel XU-2, Control Room Red light-closed Sensor Location (Normal Source Feeder Bus Voltage)
- The sensors for the normal source voltage instrumentation are transducers located on the respective buses.
L l
49 Rev. 1 l
i o
4
-1 4 s VARIABLE D25 (Continued) ,
a
- I Location of Display Display Tag Number Range Location I
Bus B Voltmeter ED-VM-752 0-5,000V Panel XU-2, Control Room-Eus C Voltmeter ED-VM-733 0-5,000V Panel XU-2, Control Room
!! Bus D Voltmeter ED-VM-754 0-5,000V Panel XU-2, Control Room d
Sensor Location (Normal Source Series Breakers to Emergency Buses) .
l Breaker No. Sensor Location AE6 Breaker Auxiliary Contact 4160V SWCR El Compt. AE6 jl ,
l-AD) Breaker Auxiliary Contact 4160V, SWCR 1D Compt. 1-AD1 i
AC4 Breaker Auxiliary contact 4160V SWGR E2 Compt. AC4 N 1-AC8 Breaker Auxiliary Contact 4160V SWCR IC Compt. 1-AC8 A12 Breaker Auxiliary Contact 4160V SWCR E3 Compt. AI2
- 2-AD1 Breaker Auxiliary Contact 4160V SWCR 2D Compt. 2-AD1
' AJ9 Breaker Auxiliary Contact 4160V SWCR E4 Compt. AJ9 2-AC8 Breaker Auxiliary Contact 4160V SWCR 2C Compt. 2-AC8 i;
50 Rev. 1
~i t
- i
VARIABLE D25 (Continued) -
Location of Display Breaker No. Display Tan Number Range Location AE6 Position Light ED-ZL-951 Green-open/ Red-Closed Panel XU-2, Control' Room 1-AD1' Position Light EP-ZL-951. Creen-open/ Red-Closed Panel XU-2, Control Room AC4' Position Light ED-ZL-958 Creen-open/ Red-Closed Panel XU-2, Control Room 1-AC8 Position Light ED-ZL-958 Creen-open/ Red-Closed Panel XU-2, Control Room A12 Position Light ED-ZL-963 Creen-open/ Red-Closed Panel XU-2, Control Room .
.2-AD1 Position Light ED-ZL-963 Creen-open/ Red-Closed Panel XU-2, Control Room' '
AJ9 Position Light ED-ZL-969 Creen-open/ Red-Closed Panel XU-2, Control Room i 2-ACC Position Light ED-ZL-969 Creen-open/ Red-Closed Panel XU-2, Control Room Sensor Location (DC Standby Power)
The sensors for the 125/250V DC bus and 24/48V DC bus are the battery charger output terminals.
Location of Display
! Display Tag Number Range location Voltage Indicator BAT-VM-737 0-150V XU-1, control Room Voltage Indicator . BAT-VM-738 0-150V XU-1, contrcl Room Voltage Indicator BAT-VM-739 / .0-150V XU-1, Control Room Voltage Indicator BAT-VM-740 0-150V XU-1, control Room l Voltage Indicator BAT-VM-741 0-60V XU-1, Control Poom
[ Voltage Indicator BAT-VM-741-1 0-60V XU-1, Control Roon j Voltage Indicator BAT-VM-742-1 0-60V XU-1, Control Room Standby Instrument Air Pressure
{
- Currently, there is no control roo[a indication for standby instrument air pressure. IA-PI-3785 and IA-PI-3786 provide local pressure indications. The standby instrument air compressors are presently scheduled to be spared and the containment pump back system will provide pneumatic power to systems in the primary containment. The. pump back
, system being installed by PM 82-008 and PM82-009 will provide for pressure indication in the control room. If the current plans to spare the standby instrument air compressors change, the need for pressure indication will have !
to be re-evaluated.
i h) Schedule: No changes are required for the diesel generator, normal source feeder, or DC battery instrumentation.
The instrument air instrumentation will be scheduled for completion during refuel f5 for both 3 units.
+
51 Rev. I 1
4
. VARIABLE D26'- TURBINE BYPASS VALVE POSITION-Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range Plant Designer Selected Green light-closed / Red light-open-(b) Environmental Qualification No' Note 1 (c) Seismic Qualification
- No Note 1 (d) Quality Assurance No Note 2 .
+,
(e) Power Supply Not-IE High Reliability ,
(f) Redundence No No Sensor Location All sensors are position switches located on the ten valves in the Turbine Steam Chest and are listed below by tag number.
MS-ZS-BVCSI MS-ZS-BVOSI MS-ZS-BVCS2 MS-ZS-BVOS2 MS-ZS-BVCS3 MS-ZS-BVOS3 MS-ZS-BVOS4 MS-ZS-BVOS4 MS-ZS-BVCSS MS-ZS-BVOSS MS-ZS-BVCS6 MS-ZS-BVOS6 MS-ZS-BVCS7 MS-ZS-BVOS7 MS-ZS-BVCS8 MS,-ZS-BVOS8 MS-ZS-BVCS9 MS-ZS-BVOS9 '
MS-ZS-BVCS10 MS-ZS-BVOS10 (g) Location of Display Display Tag Number Range Location Position Light EHC-CS-436 Open/Close Panel XU-2, Control Room The indicating lights are part of- the EHC (electro hydraulic control) panel insert located on Panel XU-1. ,
i (h) Schedule: No changes required.
NOTE: The instrumentation above is for Unit 2. Unit 1 is similar but has only four '
bypass valves.
52 Rev. 1
1 E.
VARIABLE D27 -
CONDENSER HOTWELL LEVEL Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range Plant Designer Selected '
-24 to +24 inches ,
(b) Environmental-Qualification No Note 1- ,
(c) Seismic Qualification No Note 1 (d) Quality Assurance No Note 2 (e) Power Supply Non-IE High Peliability (f) Redundance No No Sensor Tag Number Range Location Transmitter CO-LT-2 0-48 inches Condenser 1A Transmitter CO-LT-3 0-48 inches condenser lA Transmitter CO-LT-4 0-48 inches Condenser 1B Transmitter CO-LT-5 0-48 inches Condenser IB (g) Location of Display Display Tag Number Range Location Level Indicator ,CO-LI-2 -24 to +24 inches Panel XU-2, Control Room Level Indicator CO-LI-3 -24 to +24 inches Panel XU-2, Control Room Level Indicator CO-LI-4 -24 to +24 inches Panel XU-2, Control Room Level Indicator CO-LI-5 -24 to +24 inches Panel XU-2, Control Room (h) Schedule: No changes to the instrumentation are required.
~
53 Rev. 1 S
VARIABLE D28 - CONDENSER VACUUM Recommended by RG 1.97 Provided by Brunswick
- (a) Instrument Range Plant Designer Celected 0 to 30 in. Hg Vac l (b) Environmental Qu.alification No Note 1 ,
(c) ' Seismic Qualification .No ' Note 1 (d) Quality Asserance High Quality. Commercial Crade Note 2
. (e) Power Supply Non-lE High Reliability 4
(f) Redundance / Sensor Location No No Sensor Tag Number Range Location Transnitter 00-PT-23-1,2 0-30 in. Hg. Vac. IR-TB-6 Turbine Bldg.
- (g) Location of Display, Display Tag Number Range Location i Pressure Recorder OC-PR-23 0-30 in. Hg Vac. XU-2, Control Roori 4
(h) Schedule: No changes are required for the above instrumentation.
i.
i 4
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54 Rev. 1 9
t 4-VARIABLE D29 -
CONDENSATE PUMP AND BOOSTER PUMP STATUS J
Recommended by RC 1.97 'Provided by Brunswick (a) Instrument Range Plant Designer Selected Green light - off
- . Red light - on -
-(b) Environmental Qualification No Note 1 (c) Seismic Qualification No Note 1 (d) Quality Assurance High Quality Commercial Grade Note 2 (e) Power Supply Non-1E lE ,
(f) Redundance / Sensor Location No No 4
Sensor- Location '
Condensate Pump A Breaker Auxiliary Contact 4160V SWCR D
- B Breaker Auxiliary Contact 4160V SWGR C C Breaker Auxiliary Contact 4.50V SWCR D Condensate Booster Pump A
- Breaker Auxiliary Contact 4160V SWCR C B Breaker Auxiliary Contact 4160V SWCR'A C Breaker Auxiliary Contact 4160V SWGR A a
55 Rev. 1 9
VARIABLE D29 - CONDENSATE PUMP AND BOOSTER PUMP STATUS (CONT'D)
(g) Location of Display Condensate Pump Display Tag Number Location A Position Light CO-CS-305 Panel XU-2, Control Room
- B Position Light CO-CS-306 . Panel XU-2. Control Room C Position Light CO-CS-307 Panel XU-2, Control Room Condensate Booster Pump A Position Light COD-CS-311 -
Panel XU-2, Control Room ;
B Position Light COD-CS-312 Panel XU-2, Control Room C Position Light COD-CS-313 Panel XU-2, Control Room (h) Schedule: No changea required.
4 56 Rev. I a.
l i
i i 1 ,
I .
i VARIABLE - El PRIMARY CONTAINMENT AREA RADIATION-HICH RANCE Recommended By RC 1.97- Provided by Brunswick (a) Instrument Range IR/hr to 10 R/hr ~1R/hr to 10 R/hr ,
'I
- ! (b) Environmental Qualification Yes Note 1
.i J (c) Seismic Qualification Yes Note 1 d
Note 2 N (d) Quality Assurance Yes
"] '
(e) Posar Supply 1E. IE
-(f) Redundance & Sensor Location Yes Yes r Sensor Tag No. Range Location Radiation Detector D22-RM-4195 1 R/hr to 10 R/hr Drywell AZ 64 El 30'6"
" " " " D22-RM-4196 " " "
Drywell AZ 15 El 57'7" i
- D22-RM-4197 Drywell AZ 239 El 23'
? D22-RM-4198 ," Drywell AZ 195 El 57'7" 1
5 (g) Location of Display i
i Display Tan No. Range Location 4
' 7 j Indicator D22-RI-4195 1 R/hr to 10 R/hr XU-75 Electronic Equip. Room
- Indicator D22-RI-4196 l Recorder D22-RR-4195 Indicator D22-RI-4197 XU-79 Indicator D22-RI-4198
! Recorder D22-RR-4197 57 Rev. 1 i
a i
4 I , . . - - .
i
.i.
i VARIABLE - El (Continued)
(h) Schedule - No changes required.
- i 3
'l 1
9 i
58 Rev. ]
4 4
i 7
VARIABLE E2 - Reactor Building or Secondary Containment -
High range monitoring of this variable Area Radiation is not required for Brunswick. The Reactor Building vent is closed when the radiation level reaches S mr/hr f and secondary containment atmosphere is routed through the standby gas treatment system. See Brunswick position paper.
i t
i .
3 i
4 l
i i
l i
i i'
59 Rev. 1 i
l
VARIABLE E3 - Radiation Exposure Rate (inside buildings of areas -
See Variable C14. The Brunswick where access is required to service equipment Plants are not designed to allow important to safety) , servicing equipment following an accident. This variable is not required.
H 4
4 l
A 4
4 4 ,
L i
i I
j - .ev. 1 4
VARIABLE E4.- NOBLE CASES AND VENT FLOW RATE VARIABLE E5 - PARTICULATE AND HALOCEN -
. Drywell Purge, Standby das Treatment System Purge. Not required. Brunswick discharges through the Standby Cas Treatment System and t'ien through i common vent (stack). ,
. Secondary Containment Purge Not required, on high radiation the reactor vent closes and secondary containment atmosphere is ,
routed through the Standby Cas Treatment System and then through common vent (stack).
. Secondary Containment (reactor shield building Not applicable.
annulus', if in desigr.)
. Auxiliary Building Not applicable.
. Common Plant Vent /Thrbine Building Vent .
Recommended by RC 1.97 Provided by Brunswick r
(a) instrument range ~
Stack Flow 0-Ig0%designflow See Below Stack gas 10- " " '
Stack Particialated Halogen eCi/cc-10hAC1/cc 10-3pci/cc -10 AC1/cc " "
Turbine Bldg Vent flow " "
Turbine Bldg Vent gas 0-1g0%designfgow " "
T.2rbine Bldg Particulate &
' 10 3 pCi/gc -10 Aci/cc " "
10- - 10 pCi/cc Halogen (b) Environmental Qualification Noble cas Yes See Note 1 Flow Rate Yes See Note 1 Particulate & Halogen No -
61 Rev. 1 4
w
- O
VARIABLE E4 - NOBLE CASES AND VENT FLOW RATE !
r,
. VARIABLE E5 - PARTICULATE AND HALOCEN
, i.
E' . 'Drywell Purge, Standby Cas Treatment System Purge.. Not required. Brunswick discharges through the 5 Standby Cas Treatment System and then through common vent (stack) . j ,
. Secondary Containment Purge Not required, on high radiation the reactor vent
> closes and secondary containment atmosphere is ,
routed through the Standby Cas Treatment System and then through common vent (stack).
. Secondary Containment (reactor shield building Not applicable.
annulus *, if in design)
. Auxiliary Building Not applicable. '
. Common Plant Vent / Turbine Building Vent [
Recommended by RC 1.97 Provided by Brunswick (a) Instrument range
- Stack Flow See Below Stack gas 0-lg0%designfgow " "
10- pCi/cc -10 ACi/cc 2
Stack Particulated Halogen 10 Aci/cc -10 Aci/cc " "
Turbine Bldg Vent flow " "
Turbine Bldg Vent gas 0-1}0%designfgow " "
Tulibine Bldg Particulate '& ~ ' 10-} pC1/gc -10 pC1/cc " "
10- - 10 pCi/cc Halogen (b) Environmental' Qualification Noble Gas Yes See Note 1 Flow Rate Yes See Note 1 Particulate & Halogen No -
1 61 Rev. 1 -
4 t
t -
VARIABLE E4, E5 Recomumended By RC 1.97 Provided by Brunswick' (c) Seismic Qualification No !*
(d) Quality Assurance Not Required See Note 2 (e)' Power Supply High Reliability High Reliability (f) Redundance & Sensor Location No Partially as shown below Sensor Tag No. Range Imcation Function
-1 Radiation Detection D12-K600A 10 -10 CPS Local Stack monitor
" ~" " " " " "
D12-K6008 -
6 Local Stack monitor' VA-AQH-3215 10-10 CPS Incal Turbine Vent D12-RE-4561 High- IR-TB-31 TB Vent Rad Mon
- D12-RE-4562 Mid D12-RE-4563 Low -
D12-RE-4573 High IR-SH-34 OG Stack Rad Mon D12-RE-4574 Mid D12-RE-4982 Low Flow Transmitter VA-FT-3358 0-15000 SCFM Local Turbine Vent Flow Transmitter VA-FT-3359 0-100,000 SCFM Local Plant Stack n
(g) Location of Display Display Tag No. Range Location Service 6
Recorder D12-RR-R600A 10~ -10 CPS XU-3 Control Room Stack Recorder " " " " " " "
2 D12-RR-R6QOB Stack 10 -10 6. CPS 1 " "
Indicator VA-AQH-3215-1 XU-55 " Turbine Vent Particulate i Indicator VA-AQH-3215-2 Turb. Vent. Iodine I
Indicator VA-AQH-3215-3 XU-55 Turb. Vent Gas Recorder D12-RR-4548-1 10 TB Vent Rad Mon Recorder D12-RR-4548-2
~ to 10} uci/cc XU-75 Control Room "
10[ to 10 5 ,", ,", ", , ",
Recorder D12-RR-4548-3 10 to 10 I 13 " " " "
Effluent Recorder D12-RR-4549 Radiation Recorder D12-RR-4599-1 10 f to 10- uC1/Sec ~'
10-~4 to 10 "* * "" * "
Radiation Recorder D12-RR-4599-2 10 to 10 ~2 " "I!** " " " "
-I 0 " " " "
i Radiation Recorder D12-RR-4599-3 lo to 10
I " " " "
Effluent Recorder D12-RR-4600 10 to 1013 UC1/Sec 62 Rev. 1 i >
. es a 6 < -
VARIABLE E4, ES (g) Location of Display (Continued)
Display Tag No. Range Location Service Totaliser . VA-F1Q-3358 XU-62 contral Room Turbine Vent Totalizer VA-F1Q-3358 Stack Recorder VA-FR-3356 0-200000 SCFM XU-51 Control Room Stack Recorder " " "
VA-FR-3356 0-15000 SCFM Turbine Vent (h) Schedule - TMI Plant Hodifications80-034, 80-035 and 80-036 have provided the instrumentation to monitor the stack and turbine building vents.
4 t
a 63 Rev. 1
+
VARIABLE E6 - Radiation Exposure Meters -
Not rciquired to be implemented. Refer (continuous indication at to NRC Errata dated July 1981 and fixed locations) RG 1.97 Rev. 3.
4 4
4 64 Rev. 1 i
VARIABLE E7 - AIRBORNE ' ADI0 HALOGENS AND PARTICULATES (Portable Sampling with onsite analysis capability)
Recosamended by RC 1.97 Provided by Brunswick
~ ~
(a) Instrument Range 10 ' Ci/cc to 10~ C1/cc' 10 4 C1/cc to 10" Ci/cc (b) Environmental Qualification No specific provision No 4
(c) Seismic Qualification No specific provision No [
(d) Quality Assurance High Quality Commmercial High Quality Comunercial Crade Crade 2 (e) Power Supply No specific provision -
. (f) Redundance & Sensor Not Required Yes l Location Item Range Location ND 66 & ND 6620 -10 -2 10 C1/cc to"10 "
Ci/cc Counting Room l ND 6620 Mobile Station l (g) Location of Display - Counting Room, Mobile Station. The Technical Support Center will also l have an ND-66 linked to the ND 6620 in the counting room.
s (h) Schedule - No changes are required.
t
, 65 Rev. 1 m m w _ __
VARIABIE M8 - PLANT AND ENVIRONS RADIATION .
(PORTABLE INSTRUMENTATION)
Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range _3 4 Photons 10 R/hr to 10" R/hr" Beta & low energy photons (b) Environmental Qualification No opec.ific provisions -
(c) Seismic Qualification No specific provisions -
(d) Quality Assurance High Quality Commercial High Quality Commercial Grade Grade (e) Power Supply No specific provision Battery Powered (f) Redundance & Sensor Location Not Required Yes - multiple units provided Item Quantity Range Measurement Location ES-20 50 0 R/hr -2 R/hr Photons Service Bldg.
E-400 6 0 - 200 ar/hr Photons Minirad 28 0 - 5 R/hr Photons PIC-6A 30 Photons PRM-7 6 051000 10- R/hrR/hr
-5 x 10-3R/hr Photons " " "
Ro-7 2 0 - 20,000 R/hr Photons, beta & low energy photons " "
Ro-2 20 0 - 5 R/hr Beta & low energy photons Teletektor 35 0 - 1000 R/hr Photons
' Ro-2A 15 0 - 50 R/hr Beta & low energy photons (g) Location of Display - Display is integral part of portable instrument.
(h) Schedule - No changes required.
66 Rev. 1
i f VARIABLE E9 - Plant and Environs Radioactivity (Portable Instrumentation)
]
Recommended by Provided by Brunswick
, RC 1.97 l
t.',: . Instrusaent Range Multichannel Cassna Ray ND-66 Multichannel Causia Spectrometer Ray Spectrometer b) Environmental Qualification No specific provision -
c) -Seismic Qualification No specific provision -
d) Quality Assurance High Quality High Quality Commercial Crade Comunercial Grade
, e) Power Supply Ne specific provision -
f) Redundance & Sensor Location Not Required Yes i
ND 66 located in Counting Room ,,
ND 6620 located in Mobile Lab 3
g) Location of Display - Display is integral part of portable instrument. ,
h) Schedule -
No changes are required.
t
+
67- Rev. 1 i
l i
15
i '
Variable E10 - Wind Direction
- - Variable Ell - Wind Speed Variable E12 -
Estimation of Atmospheric Stability Recommended by RC 1.97 Provided by Brunswick t
,,f Instrument Range E10 0 to 360 (1 5 accuracg 0 to 540 , i 5.4' with a deflection of 15 ).
Starting speed 0.45 mps (1.0 mph). Damping ratio between 0.4 anJ 0.6, distance constant 12 meters.
Ell 0 to 30 mps (67 mph) 1 0.22 0 to 125 mph, i .4 mph ups (0.5 mph). . Accuracy for wind speeds less than 11 mps (25 mph) with a starting threshold of less than 0.45 mps (1.0 mph).,
E12 Based on vertical tempera- Differential temperature
. ture difference from primary System + .186 F over system.-5 C to 10 C (-9"F ambient temperature range to 1"*F and i .15 C accur- from -50 C to + 30 F acy per 30 meter intervals
. (1 3 F accuracy per 164-foot intervals) or analogous range for alternative '
stability estimates.
b) Environmental Qualification No specific provision High Quality Commercial c) Seismic Qualification No specific provision No 68 Rev. 1 i
- , . Variable E10 (Continued)
! Variable Ell (Continued) i Variable E12 (Continued) Recommended by RC 1.97 Provided by Brunswick d) Quality Assurence High Quality Commercial High Quality Commercial a
e) Power Supply No specific provision Conventional Power Sources f) Redundance and Sensor Location Redundancy not required No redundancy Sensors are located at the Meteorological Tower i g) Location of Display - Dispir.ys are located in an environmentally controlled -
shelter located near the tower. A computer system polls the meteorological station, and provides print-outs in the. control room for operators.
h) Schedule - Brunswick will replace the existing system with new equipment which will fully meet RC 1.97 requirements. The new system is scheduled to go into operation. December, 1983. ,
1 i
N 4
1 4
69 Rev. 1
e i
VARIABLE E13 - Primary Coolant and Sump (ANALYSIS CAP &BILITY ON SITE)
Recoussended by RG 1.97 Provided by Brunswick a) Instrument Range l Cross Activity 1G uCi/a1 to 10 Ci/ml 1 uCi/ml to 10 uCi/ml j- Camma Spectrum Isotopic Analysis Isotopic Analysis Boron Content 0 to 1000 ppm 20 to 6000 ppa Chloride Content 0 to 20 ppa 0.5 to 20 ppm Dissolved Hydrogen or Total Gas 0 to 2000 cc (STP)/Kg $ 1 to 100%
Dissolved oxygen 0 to 20 ppm 5 1 to 30%
pH 1 to 13 1 to 14 b) Environmental Qualification No specific provision Sampling System will be -
qualified. Analysis equip-ment is high quality cosmercial.
, c) Seismic Qualification No specific provision Sampling system will be
- seismically qualified.
l Analysis equipment has not been qualified.
d) Quality Assurance ' '
High Quality Conenercial Sampling system has full Grade QA Program comunitment.
Analysis equipment is i high quality comunercial .
grade.
i i
70 Rev. 1 1
4 VARIABLE E13' (Continued)
Recommended by RG 1.97 Provided by Brunswick i
(e) Power Supply No specific provision Sampling System will be.1E power. Analysis equipment is powered from conventional (
sources.
(f) Redundance & Sensor Location Redundancy not required -
i The Post Accident Sampling System allows samples of primary coolant to be taken from a remote station in the Turbine Building breezeway. Analyzing equipment is located as follows:
Cross Activity and Camma Spectrum -
Counting Room, Mobile Trailer Chemical Analysis - Chemistry Lab (f) Location of Display r The chemistry analysis is made in the t:hemistry Lab and the results logged. Cross activity and gamma spectrum displays are available in the Counting Room and Mobile Trailer.
(h) Schedule: TMI Plant Modifications80-028 and 80-029 have provided the Post Accident Sampling System for Unit I and 2, respectively. ,
9 e
71 Rev. I 1
VARIABLE E14 - Containment Air ,
Recommended by RC 1.97 Provided by Brunswick (a) Instrument Range Hydrogen Content 0 to 30% 3 1 to 100%
0xygen Content. O to 30% 5 1 to 30%
Camma Spectrum (Isotopic Analysis) Isotopic Analysis (b) Environmental Qualification No specific provision Sampling system will be environmentally qualified.
Anal.ysis equipment is high quality commercial.
(c) Seismic Qualification No specific provision Sampling System will be seismically qualified.
Analysis equipment has not been qualified.
(d) Quality Assurance High Quality Comunercial Brunswick QA program applies Grade to the sampling system.
Analysis equipment is high quality comunercial grade.
(e) Power Supply No specific provision Sampling System will be 1E power. Analysis equipment is powered from conventional sources.
72 Rev. 1 9
I .
[
Variable E14' (Continued)
Recommended by RC 1.97 Provided by Brunswick (f) Redundance & Sensor Location Redundancy'Not Required -
The Post Accident Sampling System allows samples of primary coolant to be taken from a remote station in the Turbine Building. breezeway. The analysis equipment is located in the Chemistry Lab.
(g) location of Display - The display is located 'in the Chemistry Lab and sample resulta are logged.
(h) Schedule: TMI Plant Hodifications80-028 and 80-029 have provided the Post Accident Sampling System for Units 1 and 2, respectively.
e I
1
)
73 Rev. 1. ,